ML14162A458

Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2, Regulatory Audit in Support of the License Amendment Request to Implement Risk-Informed, Performance-Based, Fire Protection Program as Allowed by Title 10 of the Code

ML14162A458
Person / Time
Site:	Diablo Canyon
Issue date:	06/12/2014
From:	Hamzehee H, Klein A NRC/NRR/DRA/APLA
To:	Markley M Plant Licensing Branch IV
Fields L, NRR/DRA, 415-1186
References
TAC MF2333, TAC MF2334
Download: ML14162A458 (10)

Text

June 12, 2014 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Hossein Hamzehee, Chief /RA/ S. Dinsmore for/

PRA Licensing Branch Division of Risk Assessment Office of Nuclear Reactor Regulation Alexander R. Klein, Chief /RA/ D. Frumkin for/

Fire Protection Branch Division of Risk Assessment Office of Nuclear Reactor Regulation

SUBJECT:

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNITS 1 AND 2, REGULATORY AUDIT IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT RISK-INFORMED, PERFORMANCE-BASED, FIRE PROTECTION PROGRAM AS ALLOWED BY TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PARAGRAPH 50.48(c)

(TAC NOS. MF2333 AND MF2334)

Office of Nuclear Reactor Regulation (NRR), Division of Risk Assessment staff will be conducting an audit of the Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2 (Diablo Canyon) license amendment request (LAR) to change its fire protection program to one based on the National Fire Protection Association (NFPA) standard NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, as incorporated into Title 10 of the Code of Federal Regulations, Part 50, Section 50.48(c). This memorandum provides our audit plan for the LAR in the enclosure. The audit will take place at Simulator/Training Building (Building 109) in Avila Beach, CA the week of July 13, 2014.

CONTACT: Leslie Fields, DRA/APLA 301-415-1186

M. Markley 2 Staff from the Fire Protection Branch, the Probabilistic Risk Assessment Licensing Branch, and Nuclear Regulatory Commission (NRC) Contractors from the Pacific Northwest National Laboratories and the Center for Nuclear Waste Regulatory Analysis will perform the audit. NRC regional staff may also be present as observers.

Docket Nos.: 50-275, 50-323 License Nos.: DPR-80, DPR-82

Enclosure:

As stated

ML14162A458 OFFICE NRR/DRA/APLA NRR/DRA/AFPB NRR/DRA/AFPB NRR/DRA/APLA NAME LFields PLain AKlein HHamzehee DATE 06/ 10 / 14 06/ 12 / 14 06/ 11 / 14 06/ 12 / 14 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNITS 1 & 2, REGULATORY AUDIT IN SUPPORT OF THE LICENSE AMENDMENT REQUEST TO IMPLEMENT RISK-INFORMED, PERFORMANCE-BASED, FIRE PROTECTION PROGRAM AS ALLOWED BY TITLE 10 OF THE CODE OF FEDERAL REGULATIONS, PARAGRAPH 50.48(c) (TAC NOS. MF2333 AND MF2334)

1.0 BACKGROUND

Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2 (Diablo Canyon) has submitted a license amendment request (LAR) (Reference 1) to change its fire protection program to one based on the National Fire Protection Association (NFPA) standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, as incorporated into Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.48(c).

The Nuclear Regulatory Commission (NRC) staffs review of the LAR has commenced in accordance with the Office of Nuclear Reactor Regulations (NRR) Office Instruction LIC-101, License Amendment Review Procedures. The NRC staff has determined that a regulatory audit of the Diablo Canyon LAR should be conducted in accordance with the NRR Office Instruction LIC-111, Regulatory Audits, for the staff to gain a better understanding of the licensees calculations, proposed plant modifications, and other aspects of the LAR.

A regulatory audit is a planned, license or regulation-related activity that includes the examination and evaluation of primarily non-docketed information. A regulatory audit is conducted with the intent to gain understanding, to verify information, and/or to identify information that will require docketing to support the basis of the licensing or regulatory decision. Performing a regulatory audit of the licensees information is expected to assist the staff in efficiently conducting its review or gain insights on the licensees processes or procedures. Information that the NRC staff relies upon to make the safety determination must be submitted on the docket. However, there may be supporting information retained as records under 10 CFR 50.71 and/or 10 CFR 54.37 that, although not required to be submitted as part of the licensing action, would help the staff better understand the licensees submitted information.

The objectives of this regulatory audit are to:

• Gain a better understanding of the detailed calculations, analyses and bases underlying the NFPA 805 LAR and confirm the staffs understanding of the LAR;

• Identify further information that is necessary for the licensee to submit for the staff to reach a licensing or regulatory decision; discuss requests for additional information (RAIs);

• Verify that the licensees planned process for self-approval of fire protection program (FPP) changes will meet the proposed NFPA 805 license condition and quality requirements; ENCLOSURE

• Establish an understanding of proposed plant modifications necessary to implement NFPA 805; and,

• Verify the implementation of processes or procedures that the licensee committed to as part of NFPA 805 implementation.

2.0 REGULATORY AUDIT BASIS The basis of this audit is the licensees LAR (Reference 1) and the Standard Review Plan (SRP)

Section 9.5.1.2, Risk-Informed, Performance-Based (RI/PB) Fire Protection (Reference 2).

References 3 through 7 provide additional information that will be used to support the audit.

3.0 REGULATORY AUDIT SCOPE OR METHOD The team will review the licensees NFPA 805 transition as proposed in the LAR. Key to this effort is the licensees RI/PB FPP. The team will review the fundamental FPP elements and minimum design requirements. A sample of fire protection engineering evaluations may be selected for review. In addition, the team will review, as necessary, the regulatory basis, references, licensing actions, existing engineering equivalency evaluations, and issues that the licensee has deemed previously approved.

The scope of the review of nuclear safety performance criteria may include both at-power and non-power operational modes, and may require a sample of procedures and other documentation. The compliance by fire area review will, as necessary, include multiple spurious operations, the transition of operator manual actions to recovery actions (RAs), fire protection engineering evaluations, and NFPA 805 deterministic requirements. The team may also include alternatives to compliance with NFPA 805, if any are indentified.

The team may review a sample of fire risk assessments and plant change evaluations for one or more fire areas, the evaluation of the additional risk of RAs, the licensees process for self-approving post-transition FPP changes, cumulative risk and combined changes, as well as uncertainty and sensitivity analyses. The review may also include licensee risk-informed evaluations to ensure that defense-in-depth and safety margins have been evaluated.

The team will also review the licensees assessment of the technical adequacy of the probabilistic risk assessment (PRA) model used for any risk evaluations required to transition to a RI/PB FPP, including resolution of peer review findings and licensee self-assessments. This effort may include auditing a sample of logic models and calculations in the fire PRA (FPRA) model as well as the Internal Events PRA model. The review will include, as necessary, the licensees process that has or will be implemented to maintain the quality of the Internal Events PRA and FPRA models to support self-approval of risk-informed change evaluation after transition is completed.

The scope may also include the licensees NFPA 805 monitoring program which is to establish and monitor acceptable levels of availability, reliability, and performance of fire protection systems and features relied upon for NFPA 805 compliance.

The scope may also include, as appropriate, selected plant modifications to confirm they have been appropriately characterized in the LAR. The team may review the process for controlling compensatory measures to confirm their adequacy while they remain in effect until the modifications are completed.

In addition, the audit team may review program documentation, configuration control, and the FPP quality assurance program. The FPP design basis document may be reviewed, as well as other documentation of fire hazards identification and nuclear safety capability assessments.

The review may include configuration control of the FPP design basis document, the fire PRA methods and model, and other relevant documentation as necessary. The team may also review the FPP quality assurance program, and sample fire models and fire model calculations.

Plant walkdowns may be performed as necessary to observe features of the licensees FPP and design elements of buildings within the power block.

4.0 INFORMATION AND OTHER MATERIAL NECESSARY FOR THE AUDIT The NRC audit team will require access to licensees personnel knowledgeable of the technical aspects of the Diablo Canyon NFPA 805 LAR. At a minimum, a hardcopy and electronic copy of the following documentation should be available to the audit team:

• Calculation models and supporting documentation for PRA models used in support of the LAR, including peer review history and resolution of peer review significant findings;

• Calculation models and supporting documentation for fire models used in support of the LAR;

• Procedures that have been modified or developed to transition to the NFPA 805 licensing basis;

• Procedures that have been modified or developed to maintain the NFPA 805 licensing basis after transition is completed;

• Documentation of changes made to PRA models in support of change analysis;

• Documentation about PRA configuration control and procedures to support self-approval of risk-informed plant changes after transition;

• Documentation of plant modifications or operational changes identified, screened, and considered (or planned for) during the licensees transition to NFPA 805;

• Calculations and evaluations used to transition to NFPA 805 such as plant change evaluations, engineering equivalency evaluations, and RA evaluations; and,

• Other documents, which the licensee deems as necessary to support the NRC staffs audit team, outlined under audit activities.

5.0 TEAM ASSIGNMENTS The audit will be conducted mainly by NRC staff from the Office of Nuclear Reactor Regulation (NRR) Division of Risk Assessment (DRA); Fire Protection Branch (AFPB) and the PRA Licensing Branch (APLA) staff knowledgeable in PRA, safe shutdown and circuit analysis, and fire protection engineering, will comprise the audit team. Contractors from the Pacific Northwest National Laboratories and the Center for Nuclear Waste Regulatory Analysis may be utilized to augment the technical audit team members. NRC staff from other organizations may be assigned to the team as appropriate and others may participate as observers. Observers at the audit may include NRR Program Managers and various Regional Inspectors.

The NRC Audit Team Leader will be Leslie Fields and the NRC Technical Lead will be Paul Lain. The team leader will conduct daily briefings on the status of the review and coordinate audit activities while on site. The tables below shows (1) audit milestones and schedules, in addition to (2) planned audit team composition and their assigned areas for review during the audit.

Audit Milestones and Schedule Activity Time Frame Comments RAI Clarification Call 6/25 or later Teleconference to provide clarification of draft RAIs.

NRC will present a brief team introduction and discuss the scope of the audit. The licensee should introduce team Onsite Audit Kick-Off Meeting 7/14/2014 members and give logistics for the week. In addition, the licensee should be prepared to give a virtual tour of the protected area in the plant.

Onsite Escorted Tour 7/15/2014 Tours of risk significant power block areas. 2nd day if needed 7/14/2014 - Meet with licensee to provide a summary of any significant End of Day Summary Briefing 7/16/2014 findings and requests for additional assistance.

7/14/2014 -

Provide Break-out Areas Facilitate discussion between site and staff technical areas.

7/17/2014 NRC staff will hold a short exit meeting, with licensee staff to Onsite Audit Exit Meeting 7/17/2014 conclude audit activities.

Audit Summary (see VIII) 8/31/2014 To document the audit.

Regulatory Audit Team and Assignments SRP 9.5.1.2 Audit Plan Review Areas Lead Support Section III.1.2 Modifications Team Team III.1.3 Licensee self-approval J. Robinson III.2 Fundamental FPP and Design Elements B. Metzger K. Bohlander III.3.1.2 Multiple spurious operation B. Litkett K. Bohlander III.3.2 Engineering evaluations, previous approval Team Team III.3.2.2 Operations guidance for fire modeling PB method B. Metzger K. Das III.3.2.2 Recovery Actions Team Team III.3.3 Non-power operation P. Lain K. Bohlander III.5.3-5.6 Risk assessments T. Hilsmeier G. Coles III.5.1 PRA technical adequacy T. Hilsmeier G. Coles III.5.2 DID and safety margins Team Team III.6 Monitoring program J. Robinson III.7.1-7.3 Documentation, Configuration Control, Quality J. Robinson Plant walk-downs As needed As needed 6.0 LOGISTICS This regulatory audit is planned for the week of July 14, 2014, and will last approximately 4 days. We will schedule a conference call two weeks prior to discuss the details of the Generic Audit Plan. The dates in the milestone chart are subject to change based on mutual agreement between the licensee and the NRC. An entrance meeting for this audit will be held on the first day at 9:00 AM and an exit meeting will be held on the final audit day at a mutually agreed upon

time to conclude the audit activities. The NRC audit leader will provide daily progress to licensee personnel on the second and third day of the audit.

The audit will take place at a location agreed upon by the licensee and NRC audit leader where (1) the necessary reference material and (2) appropriate analysts will be available to support the review. Because the audit scope includes NRC staff walkdowns of selected fire areas in the power block, the regulatory audit must be conducted in a location that allows for travel to the plants protected area for escorted access. Visitor access will be requested for the entire audit team. We recommend that security paperwork be handled upon arrival on the first day of the audit week.

7.0 SPECIAL REQUESTS The regulatory audit team requests the following to support the regulatory audit:

• Visitor access for all team members participating in the plant tour.

• One printer and three computers with internet access, access to the site portal, and printing capability. Wired or wireless internet access.

• Private conference room(s) (preferably outside the protected area) to support document review, breakout sessions, and audit team meetings.

• Access to the FPP documentation, including but not limited to: plant drawings depicting fire area boundaries, the Fire Hazards Analysis, Safe Shutdown Analysis, and the internal events PRA and FPRA.

• Access to licensee personnel knowledgeable in the FPP, fire modeling; safe shutdown and circuit analysis; FPRA and internal events PRA, non-power operations, radiological release analysis, and the NFPA 805 fire protection design-basis document.

8.0 DELIVERABLES A regulatory audit summary will be issued within approximately 30 days of the completion of the audit. The summary will use the guidance of NRR Office Instruction LIC-111 for content. Since formal RAIs will likely be sent prior to the audit, the summary itself is expected to be an internal memorandum from the audit team leader to the responsible supervisors. The audit summary will be placed in ADAMS.

9.0 REFERENCES

1. Letter from Barry Allen, Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2, to U.S. Nuclear Regulatory Commission, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition), June 26, 2013 (Agencywide Documents (ADAMS) Accession Nos. ML13262A411, ML13196A264, ML13196A139, and ML13196A140)

2. U.S. NRC, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, NUREG-0800, Section 9.5.1.2, Risk-Informed, Performance-Based Fire Protection Program, (ADAMS Accession No. ML092590527).

3. Title 10 Code of Federal Regulations, Part 50, Section 48 (10 CFR 50.48), Fire Protection.

4. NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Stations, 2001 Edition.

5. Regulatory Guide 1.205, Rev. 1, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants, December 2009 (ADAMS Accession No. ML092730314)

6. Nuclear Energy Institute, NEI 04-02, Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program Under 10 CFR 50.48(c), Revision 2, April 2008 (ADAMS Accession No. ML081130188)

7. Nuclear Energy Institute, NEI 00-01, Guidance for Post-Fire Safe Shutdown Analysis, Rev. 2, May 2009 (ADAMS Accession No. ML091770265)