DCL-12-081, License Amendment Request 12-02 James M. Welsch Station Director 10 CFR 50.90 Revision to Technical Specification 5.5.7. Reactor Coolant Pump Flywheel Inspection Program (TSTF-421)

License Amendment Request 12-02 James M. Welsch Station Director 10 CFR 50.90 Revision to Technical Specification 5.5.7. Reactor Coolant Pump Flywheel Inspection Program (TSTF-421)

ML12256A909
Person / Time
Site:	Diablo Canyon
Issue date:	09/12/2012
From:	Welsch J Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-12-081
Download: ML12256A909 (10)

Text

Pacific Gas and Electric Company James M. Welsch Diablo Canyon Power Plant Station Director Mail Code 104/5/502 P. O. Box 56 Avila Beach, CA 93424 September 12, 2012 805.545.3242 Internal: 691.3242 PG&E Letter DCL-12-081 Fax: 805.545.4234 Internet: JMW1@pge.com U.S. Nuclear Regulatory Commission 10 CFR 50.90 ATTN: Document Control Desk Washington, D.C. 20555-0001 Diablo Canyon Units 1 and 2 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 License Amendment Request 12-02 Revision to Technical Specification 5.5.7. "Reactor Coolant Pump Flywheel Inspection Program" (TSTF-421)

Reference:

1. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22, 2003 (68 FR 60422)

Dear Commissioners and Staff:

Pursuant to 10 CFR 50.90, Pacific Gas and Electric Company (PG&E) hereby requests approval of the enclosed proposed amendment to Facility Operating License Nos. DPR-80 and DPR-82 for Units 1 and 2 of the Diablo Canyon Power Plant (DCPP) respectively. The enclosed license amendment request (LAR) proposes to revise Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program."

The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 1O-year examination frequency to an interval not to exceed 20 years. This LAR is consistent with NRC-approved Industry/Technical Specification Task Force (TSTF) Traveler number TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)." The availability of this TS improvement was announced in the Federal Register on October 22, 2003, as part of the Consolidated Line Item Improvement Process (CLlIP) (Reference 1).

Enclosure provides a description of the proposed change and the requested confirmation of applicability. Attachment 1 to the Enclosure provides the existing DCPP Units 1 and 2 TS pages marked up to show the proposed change.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak

• Diablo Canyon

• Palo Verde

• San .onofre

• South Texas Project

• Wolf Creek

m Document Control Desk PG&E Letter DCL-12-081 September 12, 2012

, & Page 2 Attachment 2 to the Enclosure provides revised, clean-typed DCPP TS pages.

PG&E requests approval of the proposed license amendments by September 12, 2013, with implementation of the amendment within 120 days of issuance of the amendment.

PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.

This letter includes no revisions to existing regulatory commitments.

In accordance with site administrative procedures and the Quality Assurance Program, the proposed amendment has been reviewed by the Plant Staff Review Committee.

Pursuant to 10 CFR 50.91, PG&E is sending a copy of this proposed amendment to the California Department of Public Health.

If you have any questions or require additional information, please contact Mr. Tom Baldwin at 805-545-4720.

I state under penalty of perjury that the foregoing is true and correct.

Executed on September 12, 2012.

Sincerely,

~.N-..~

James M. Welsch Interim Site Vice President RNTT14231 ISAPN 50293173 Enclosure cc: Diablo Distribution cc/enc: Elmo E. Collins, NRC Region IV Michael S. Peck, NRC, Senior Resident Inspector Dean H. Overland, NRC Senior Resident Inspector Ganzalo L. Perez, Branch Chief, California Department of Public Health Joseph M. Sebrosky, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak

• Diablo Canyon

• Palo Verde

• San Onofre

• South Texas Project

• Wolf Creek

Enclosure PG&E Letter DCL-12-081 Description and Assessment of the Proposed Change License Amendment Request 12-02 Revision to Technical Specification 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" (TSTF-421)

1. INTRODUCTION

2. DESCRIPTION OF PROPOSED AMENDMENT

3. BACKGROUND

4. REGULATORY REQUIREMENTS AND GUIDANCE

5. TECHNICAL ANALYSIS

6. REGULATORY ANALYSIS

7. NO SIGNIFICANT HAZARDS CONSIDERATION

8. ENVIRONMENTAL EVALUATION

9. PRECEDENT

10. REFERENCES ATTACHMENTS:

1. Proposed Technical Specification Changes

2. Revised Technical Specification Pages 1

Enclosure PG&E Letter DCL-12-081 Description and Assessment

1. INTRODUCTION The proposed license amendment changes Technical Specification (TS) 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program." The changes are consistent with Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)." The availability of this TS improvement was announced in the Federal Register on October 22, 2003, as part of the consolidated line item improvement process (CLlIP) (Reference 1).

2. DESCRIPTION OF PROPOSED AMENDMENT Consistent with the NRC-approved TSTF-421, the proposed TS change includes the following revision to TS 5.5.7:

The examination interval for the RCP flywheels is changed from approximately 10-year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI to 20-year intervals.

3. BACKGROUND The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination," and the related NRC Safety Evaluation (SE) dated May 5, 2003.

4. REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421, WCAP-15666, and the related NRC SE.

5. TECHNICAL ANALYSIS PG&E has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLlIP. This verification included a review of the NRC staff's model SE, as well as the information provided to support TSTF-421 (including WCAP-15666 and the related SE dated May 5, 2003). PG&E has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC staff are applicable to DCPP Units 1 and 2, and justify this amendment for the incorporation of the changes to the DCPP TS.

2

Enclosure PG&E Letter DCL-12-081

6. REGULATORY ANALYSIS A description of this proposed change, and its relationship to applicable regulatory requirements and guidance, was provided in the NRC notices related to the CUIP, TSTF-421, topical report WCAP-15666, and the associated SE.

7. NO SIGNIFICANT HAZARDS CONSIDERATION PG&E has reviewed the proposed no significant hazards consideration determination, published on June 24,2003 (68 FR 37590), as part of the CUIP. PG&E has concluded that the proposed determination presented in the notice is applicable to DCPP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

8. ENVIRONMENTAL EVALUATION PG&E has reviewed the environmental evaluation included in the model SE, published on June 24,2003 (68 FR 37590), as part of the CUIP. PG&E has concluded that the staff's findings presented in that evaluation are applicable to DCPP and the evaluation is hereby incorporated by reference for this application.

9. PRECEDENT This application is being made in accordance with the CUIP referenced in Section 1.0.

PG&E is not proposing variations or deviations from the TS changes described in TSTF-421 or the NRC staff's model SE, published on June 24, 2003 (68 FR 37590).

10. REFERENCES

1. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22, 2003 (68 FR 60422)

2. Federal Register Notice: Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published on June 24, 2003 (68 FR 37590)

3. Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, "Revision to RCP Flywheel Inspection Program (WCAP-15666)," Revision 0, November 2001

4. WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination," July 2001 3

Enclosure PG&E Letter DCL-12-0B1

5. NRC letter dated May 5,2003, from H. Berkowto R. Bryan (WOG) transmitting Safety Evaluation of WCAP-15666 4

Enclosure Attachment 1 PG&E Letter DCL-12-081 Attachment 1 Proposed Technical Specification Changes

Programs and Manuals 5.5 an interval not to exceed 20 years.

5.5 Programs and Manuals (continued) 5.5.7 This program shall provide for the insp ction of each reactor coolant pump flywheel per the recommendations of Regulatory Po ition c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

In lieu of Position c.4.b(1) and c.4.b(2), a qualified in-place UT examination over the volume from the inner-bore of the f/ywh e/ to the circle one-half of the outer radius or a surface examination (MT and/or PT) of xposed surfaces of the removed flywheels may be conducted a t ' . ' "

schedule as required by ASME Section XI.

5.5.8 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

ASME OM Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to in service testing activities; and

d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

(continued)

DIABLO CANYON - UNITS 1 & 2 5.0-9 Unit 1 - Amendment No. 435,4-00, Rev 27 Page 9 of 27 Unit 2 - Amendment No. 435,49+,

Enclosure Attachment 2 PG&E Letter DCL-12-081 Attachment 2 Revised Technical Specification Pages Remove Page Insert Page 5.0-9 5.0-9

Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

In lieu of Position c.4.b(1) and c.4.b(2), a qualified in-place UT examination over the volume from the inner-bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at an interval not to exceed 20 years.

5.5.8 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:

a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:

ASME OM Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any T8.

(continued)

DIABLO CANYON - UNITS 1 & 2 5.0-9 Unit 1 - Amendment No . .m,4ge, Rev 27 Page 9 of 27 Unit 2 - Amendment No . .m,-4-9+,