ML20217A850: Difference between revisions

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==1.0      INTRODUCTION==
==1.0      INTRODUCTION==


in a letter dated February 6,1998, (which superseded an earlier submittal dated December 16, i            1997), the Wisconsin Electric Power Company submitted proposed changes to the Point Beach      j l            Nuclear Plant (PBNP) Final Safety Analysis Report (FSAR) Section 1.8 which will impact          l commitments made in the PBNP Quality Assurance Program Description (QAPD). The                  I changes concern approval authority for procedures, interviewing authority for prospective plant personnel, and reassignment of the responsibilities for maintaining the Q-List (the list of QA-scope plant equipment) from the QA organization to the line organization.
in a {{letter dated|date=February 6, 1998|text=letter dated February 6,1998}}, (which superseded an earlier submittal dated December 16, i            1997), the Wisconsin Electric Power Company submitted proposed changes to the Point Beach      j l            Nuclear Plant (PBNP) Final Safety Analysis Report (FSAR) Section 1.8 which will impact          l commitments made in the PBNP Quality Assurance Program Description (QAPD). The                  I changes concern approval authority for procedures, interviewing authority for prospective plant personnel, and reassignment of the responsibilities for maintaining the Q-List (the list of QA-scope plant equipment) from the QA organization to the line organization.
I 2.0      EVALUATION                                                                            ,
I 2.0      EVALUATION                                                                            ,
i 2.1      Procedures                                                                            I The licensee proposes to change the QAPD in the FSAR on page 1.8-7 which describes the modification process for QA program procedures. These QA procedures are not in the set of      i procedures requiring Plant Manager approval in accordance with Technical Specifications (TS).
i 2.1      Procedures                                                                            I The licensee proposes to change the QAPD in the FSAR on page 1.8-7 which describes the modification process for QA program procedures. These QA procedures are not in the set of      i procedures requiring Plant Manager approval in accordance with Technical Specifications (TS).

Latest revision as of 03:48, 21 March 2021

SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority
ML20217A850
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 03/19/1998
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217A838 List:
References
NUDOCS 9803250275
Download: ML20217A850 (3)


Text

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  • NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 20555-0001 l

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION QUALITY ASSURANCE PROGRAM DESCRIPTION CHANGES FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 1

DOCKET NOS. 50-266 AND 50-301

1.0 INTRODUCTION

in a letter dated February 6,1998, (which superseded an earlier submittal dated December 16, i 1997), the Wisconsin Electric Power Company submitted proposed changes to the Point Beach j l Nuclear Plant (PBNP) Final Safety Analysis Report (FSAR) Section 1.8 which will impact l commitments made in the PBNP Quality Assurance Program Description (QAPD). The I changes concern approval authority for procedures, interviewing authority for prospective plant personnel, and reassignment of the responsibilities for maintaining the Q-List (the list of QA-scope plant equipment) from the QA organization to the line organization.

I 2.0 EVALUATION ,

i 2.1 Procedures I The licensee proposes to change the QAPD in the FSAR on page 1.8-7 which describes the modification process for QA program procedures. These QA procedures are not in the set of i procedures requiring Plant Manager approval in accordance with Technical Specifications (TS).

The proposed change would delete the following sentence:

The [ quality assurance] manual procedures and subsequent revisions are approved by the designated section manager within the NPBU [ Nuclear Power Business Unit) assigned primary responsibility for the procedure.

The proposed changes would replace the deleted sentence with the following:

Prior to initial issuance er subsequent revisions, [ quality assurance} procedures

, are reviewed by an individual (s) knowledgeable in the subject area addressed by l the procedure. As a minimum, procedures are approved for initialissuance, l subsequent revision, and cancellation by the cognizant group head.

l l

I 9803250275 980319 PDR ADOCK 05000266 P PDR a

, ANSI N18.7-1976/ANS-3.2, Section 5.2.1.5, " Review, Approval and Control of Procedures,"

states:

These measures shall assure that documents, including revisions or changes, are reviewed for adequacy by appropriately qualified personnel and approved for release by authorized personnel.

Plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no less frequently than every two years to determine if changes are necessary or desirable.

Procedures shall be approved as designated by the owner organization before initial use. Rules shall be established which clearly delineate the review of procedures by knowledgeable personnel other than the originator and the approval of procedures and procedure changes by authorized individuals.

Changes to documents shall be reviewed and approved by the same organizations that perform the original review and approval unless the owner organization designates another qualified organization.

The licensee is maintaining consistency with ANSI N18.7-1976/ANS-3.2, Section 5.2.15,

" Review, Approval and Control of Procedures." This is the ANSI standard the licensee is committed to follow. The licensee is also maintaining its TS 15.6.8, " Plant Operating Procedures," commitment which requires all major procedures listed in TS 15.6.8.1 (except TS 15.6.8.1.4) and TS 15.6.11 be approved by the Manager prior to implementation. The licensee is maintaining this commitment because the QA procedures are not listed in TS 15.6.8.1 or TS 15.6.11. The licensee's reduction in commitment continues to comply with the criteria of Appendix B to 10 CFR Part 50.

2.2 IDkrviewing The proposed change to the QAPD in the FSAR on page 1.8-17 revises the description of individuals responsible for interviewing prospective plant personnel for hire. The proposed change describes that the cognizant group head will conduct the interviews rather than " senior plant management," and it also describes that in most cases the " applicable section manager" will conduct interviews rather than the " Manager - Nuclear Operations." The responsibility for interviewing does not impact the required qualifications of plant personnel; therefore, the reduction in commitment continues to comply with the criteria of Appendix B to 10 CFR Part 50, 2.3 Q-Litt The proposed change to the QAPD in the FSAR on page 1.8-5 modifies the QA-scope classification engineering activities and Q-List maintenance activities on the list of l responsibilities of the QA organization. The proposed change would delete the following sentence:

1  ;

e l

- Perform QA-scope safety classification engineering activities and maintain PBNP Q-List.

The proposed change would replace the deleted sentence with the following:

Monitor QA-scope safety classification activities and assess engineering maintenance of the PBNP Q-List.

The licensee will continue to perform QA-scope safety classifications and maintain a Q-List I through the Engineering organization. The licensee will also monitor these activities through the QA organization. The reduction in commitment continues to comply with the criteria of Appendix B to 10 CFR Part 50 and Section 17.2 of NUREG-0800," Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (SRP)."

3.0 CONCLUSION

The proposed QAPD changes described above constitute a reduction in commitment in the QAPD previously approved by the NRC; however, these changes continue to satisfy the provisions in Section 17.2 of the SRP. Therefore, the proposed revision to PBNP's QAPD, dated February 6,1998, continues to comply with the QA criteria of Appendix B to 10 CFR Part 50 and is acceptable.

Principal Reviewer: M. Bugg Date: March 19, 1998 o