1. “Review and Assessment by PNRA Application Set

2. PRESENTATION LAYOUT INTRODUCTION
ESTABLISHMENT OF TECHNICAL SUPPORT ORGANIZATION (TSO)
AVAILABLE EXPERTISE
MAIN LICENSING SUBMISSIONS
REVIEW BASIS
REVIEW METHODOLOGY
REVIEW PROCEDURE
MAJOR TASKS/ACTIVITIES

3. INTRODUCTION
One of the prime responsibilities of the regulatory body is to perform review and assessment of the licensee’s submissions
In fulfillment of the requirements of PNRA Regulations, the applicants/licensees are required to submit a number of documents during different stages of the licensing process
The basic objective of review and assessment is to determine whether the operator’s submissions demonstrate that the facility complies with the regulatory requirements throughout its lifetime
The review and assessment of licensing submissions leads to regulatory decision making during the licensing process

4. INFRASTRUCTURAL ARRANGEMENT FOR REVIEW AND ASSESSMENT
In 2005, PNRA established a Technical Support Organization within the regulatory body i.e. Centre for Nuclear Safety (CNS) for performing review and assessment responsibilities
Prior to that, agreements were made with the Vendor (Chinese) regulatory body to provide assistance in review and assessment and inspection of nuclear power plants during different stages of the licensing process
55 persons mostly comprising of the fresh graduates in Nuclear Engineering and other disciplines like electrical chemical, metallurgical I & C systems engineering etc. were inducted in CNS
These officers were trained through in-house extensive training courses and fellowship visits to the Chinese regulatory body of three months duration.

5. OBJECTIVES OF ESTABLISHING CNS
Capacity building of PNRA in performing safety review and assessment of Chashma unit 2 and future nuclear power plants.
To improve the skills and knowledge of the regulatory personnel through specialized training at local and foreign institutions,
To perform independent audit calculations and conduct safety research and development work in different areas of safety analysis.
Developing strong documentation base and information centre equipped with regulatory documents (such as regulatory guides, review plans etc.) from countries such as China, USA, UK, Germany, France etc.
Developing and strengthening bilateral links with TSOs of other nuclear regulatory bodies such as USA, China and Slovak Republic etc.

6. FACILITIES PROVIDED AT CNS
A building of 9000 square feet is constructed and furnished with furniture and state-of-the art facilities.
Library was equipped with modern technical books, magazines, journals and research papers on different technical subjects for consultation in the technical assignments.
various regulatory and industrial standards like ASME Boiler and Pressure Vessel Code, RCCM Code, ANSI, ASTM, IEEE standards etc. have been acquired.
Limited scope NPP training simulator has also been developed for training of regulatory staff in familiarization of NPP system and equipment

7. ORGANIZATION AND EXPERTIESE OF DIFFERENT GROUPS OF CNS

8. MAJOR REVIEW ACTIVITIES PERFORMED
Safety Analysis Reports (C-2 SAR)
Site Evaluation Reports of K2, C3 & C4 SER
Safety Analysis Reports of C-3/C-4 and K-2/K-3
Periodic Safety Reports (PSR) of C-1 and K-1
Site Evaluation Repot (SER) of K-2
KANUPP revised FSAR
Probabilistic Safety Assessment (PSA) reports
Commissioning Program & Related Activities
Review of Plant Modifications of K-1, C-1 & C-2

9. USE OF EXTERNAL SUPPORT DURING REVIEW AND ASSESSMENT
PNRA signed bilateral agreements with the National Nuclear Safety Administration (NNSA) of China.
The primary concern of hiring external technical support was to enhance the effectiveness of licensing process of C-1 and C-2
According to a protocol signed in 2004, Center for Nuclear Safety (CNS) of PNRA and Nuclear Safety Center (NSC) of NNSA were designated as counterparts of each other.
The major areas for bilateral cooperation included the following:
review and assessment of licensing submissions such as SAR, PSA reports, commissioning program etc.
Inspections during construction, manufacturing, installation and commissioning stages of C-2

10. AREAS OF EXPERTISE IN AUDIT CALCULATIONS AND COMPUTER CODES
Areas of Safety Analysis
Thermal hydraulics
DBA and Beyond DBA Analysis
Radiological Consequence Analysis
Stress Analysis
CFD Analysis
Seismic Analysis
Probabilistic Safety Assessment
Fuel Analysis
Analytical Tools
RELAP 5/MOD3.4
CONTAIN
MELCOR
GALE
MACCS
PEPS ANSYS
FLUENT
RISKSPECTRUM SAP 2000
FUELSIM

11. MAJOR ANALYSIS TASK PERFORMED TO SUPPORT REVIEW AND ASSESSMENT
CFD Analysis of Surveillance capsule of C -1
Mechanical Integrity Evaluation for SG tubes of K-1 Steam Generator
Analysis of Molten Core Concrete Interaction (MCCI) in reactor cavity in case of a severe accident at C-1
Analysis of Station Blackout sequence at C-1
Audit calculations of DBA and BDBA analysis presented in C-2 FSAR

12. REVIEW METHODOLOGY
Review of Design Basis of Structure Systems and Components
Review of Functional Requirements
Checking of compliance against the general design and specific acceptance criteria
Review of systems PIDs
Perform audit calculations of selected analysis by using available computer codes
Prepare evaluation findings

13. MAIN LICENSING SUBMISSIONS
Safety Analysis Reports (SARs);
Quality Assurance Program (QAP);
Technical Specifications (TS)/Operating Policies and Procedures (OPP);
Emergency Preparedness Plan (EPP);
Radiation Protection Program (RPP);
Radioactive Waste Management Program;
In-Service/Pre-service Inspection Program;
Fire protection program;
Physical Protection plan;

14. OTHER DOCUMENTS TO BE REVIEWED
Design modifications
Modifications in Technical Specifications
Event reports
Periodic and Special Technical reports;
Reports pertaining to Refueling Outages;
Report of Periodic Safety Review

15. APPLICABLE REGULATIONS FOR REVIEW AND ASSESSMENT PROCESS
Regulations for Licensing of Nuclear Installations in Pakistan (PAK/909)
Regulations on Safety of Nuclear Power Plants; Siting
Regulations on Safety of Nuclear Power Plants; Design
Regulations on Safety of Nuclear Power Plants; Operation
Regulations on Safety of Nuclear Power Plants; QA
Regulations on Management of a Nuclear or Radiological Emergency - (PAK/914)

16. REVIEW BASIS PNRA regulations & regulatory guides
IAEA safety requirements and guides
USNRC 10CFR and regulatory guides
Standard Review Plan (NUREG-0800)
Industrial codes and standards e.g.
ASME/RCC/ACI
IEEE/IEC/ISO
ANSI/ANS

17. REVIEW PLANNING Designation of a Team Leader
Preparation of Safety Evaluation Report
Conduct of Review Meetings
Correspondence (Queries/responses)
Conduct of Review
Planning and Scheduling of Review
Scheduling of Submissions
Constitution of Review Team
Designation of a Team Leader

18. REVIEW PROCEDURE
The following steps are taken in the review & assessment of SARs
Preparation of a review schedule keeping in view the time frame allocated for the review activity
Allocation of SAR chapters to designated groups according to the area of expertise and previous experience of the reviewers.
Designation of a Core team comprising of 4-6 senior technical officers to supervise and coordinate the review activities
Allocation of Separate rooms for enabling chapter wise review and coordination among different groups
Receipt of PSAR/FSAR and related documents and reports from the licensing Directorate NSD which has interface with the licensee

19. REVIEW PROCEDURE
If submitted documents are incomplete, the same are sent back to NSD for acquisition of complete information from the licensee so that review and assessment can be carried out thoroughly and effectively.
After getting complete information, PSAR/FSAR is docketed for review
The review is performed in three phases:
Phase-1: Review of format & contents of PSAR/FSAR in accordance with R.G 1.70.
Phase-2: Detailed review on the basis of Regulations, regulatory guides, industrial standards
Phase-3: Review on the basis of feedback from national and international operating experience, generic safety Issues, international good practices

20. REVIEW PROCEDURE
Finalization of the queries/observations by the review team in consultation with the Director of TSO
Review of the queries/observations by the core team for evaluation and finalization.
Finalized queries sent to NSD for internal approval and onward communication to the applicant/licensee for response.
Receive responses of queries from the Licensee through NSD
Perform review of the responses and preparation of regulatory positions and action sheets
Conduct review meeting with the licensee to discuss the regulatory position and signing of action sheets.
Preparation of Safety Evaluation Report (SER) and Identification of safety issues/licensing conditions

21. REVIEW AND ASSESSMENT PROCESS
SAR Received from applicant
Not Acceptable
Cursory Review for docketing of SAR
SAR sent back to Licensee
Acceptable
Finalized queries sent to the Licensee
Review of Format and Content
Responses received from Licensee
Detailed Review and Assessment
Review and preparation of regulatory position
Queries discussed and evaluated by TSO Core team
Review Meetings with the Licensee
Meeting with Core Team and Review Team
Preparation of Safety Evaluation Report (SER)

22. REVIEW OUTCOME
Final out come of the review and assessment by the regulatory body
The format of SER is according to the format of relevant chapter of NRC Standard Review Plan (NUREG-0800)
Main Contents of SER (for each chapter of SAR)
Review Basis
Review Details
Conclusion
List of queries raised
List of pending issues requiring action by the licensee
License conditions of review (if any)

23. CONCLUSION
The establishment of internal TSO has greatly helped PNRA in strengthening its licensing and regulatory decision making process by:
Performing indigenous expertise of in-depth technical review of different areas which led to enhancement of safety of nuclear installations
Performing audit of the analytical calculations presented by the licensee in the safety analysis reports to support review and assessment
Performing safety research and development activities related to emerging safety issues

24. THANK YOU