JAFP-10-0069, Response to Request for Additional Information Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves
| ML101580384 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/03/2010 |
| From: | Peter Dietrich Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-10-0069, TAC ME2810 | |
| Download: ML101580384 (5) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 JAFP-10-0069 June 03, 2010 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Response to Request for Additional Information Re: James A. FitzPatrick Nuclear Power Plant Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves (TAC No. ME2810)
James A. FitzPatrick Nuclear Power Plant Docket No.
50-333 License No. DPR-59
References:
- 1. Entergy Letter, JAFP-09-0132, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves (TAC No. ME2810), dated November 23, 2009
- 2. Entergy Letter, JAFP-10-0039, Response to Request for Additional Information Re: James A. FitzPatrick Nuclear Power Plant Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves (TAC No. ME2810), dated March 18, 2010
- 3. NRC Request For Additional Information Regarding James A. FitzPatrick Nuclear Power Plant Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves (TAC No.
ME2810), dated March 29, 2010
- 4. Entergy Letter, JAFP-10-0059, Response to Request for Additional Information Re: James A. FitzPatrick Nuclear Power Plant Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves (TAC No. ME2810), dated May 11, 2010
- 5. NRC Request For Additional Information Regarding James A. FitzPatrick Nuclear Power Plant Application for Amendment to Modify the Technical Specifications Requirements for Testing of Safety/Relief Valves (TAC No.
ME2810), dated May 12, 2010 Pete Dietrich Site Vice President - JAF
JAFP~10-0069 Page 2 of 3
Dear Sir or Madam:
On November 23,2009, Entergy Nuclear Operations, Inc. (ENO), submitted an application for amendment to the Technical Specifications (TS) for the James A. FitzPatrick Nuclear Power Plant (JAF), that would revise the surveillance testing requirements for safetylrelief valves
[Reference 1]. On March 18, 2010, JAF resubmitted the application for amendment [Reference 2] based on a Nuclear Regulatory Commission (NRC) request for additional information (RAI).
On March 29, 2010, JAF received a folJow~up RAI [Reference 3], based on NRC review of the initial RAI response. That request was clarified in conference calls with the staff on March 29, 2010, and April 5, 2010. On May 11,2010, JAF responded to the follow-up RAt from the NRC staff [Reference 4]. On May 12, 2010, JAF received another follow-up RAI question [Reference 5], based on NRC review of the follow-up RAI response [Reference 4]. That request was clarified in a conference call with the staff on May 13, 2010.
Based on the clarifying discussions with the staff, ENO is sUbmitting the attached response to the follow-up RAI question [Attachment 1].
The attached response does not affect the No Significant Hazards Determination submitted with the revised amendment application, dated March 18, 2010.
There are no new commitments made in this letter.
Questions concerning this submittal may be addressed to Mr. Joseph Pechacek, Licensing Manager, at (315) 349-6766.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 3rd d Pete Dietn h Site Vice President - JAF PD/JP/ed Attachments:
1.
Response to Request for Additional Information Question cc: next page
JAFP-10-0069 Page 3 of 3 Mr. Samuel Collins Mr. Paul Eddy Regional Administrator, Region I New York State Department of Public U. S. Nuclear Regulatory Commission Service 475 Allendale Road 3 Empire State Plaza, 10th Floor King of Prussia, PA 19406-1415 Albany, NY 12223 Resident Inspectors Office Mr. Francis J. Murray Jr., President U.S. Nuclear Regulatory Commission New York State Energy and Research James A. FitzPatrick Nuclear Power Plant Development Authority P.O. Box 136 17 Columbia Circle Lycoming, NY 13093 Albany, NY 12203-6399 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Washington, DC 20555-0001 Document components:
Transmittal letter JAFP-10-0069 with attachment
JAFP-10-0069 Response to Request for Additional Information Question (1 Page)
JAFP-10-0069 Response to Request for Additional Information Question Page 1 of 1 Question:
Entergy letter JAFP-10-0039, Attachment 2, section 4.0, third bullet in the paragraph on proposed testing, describes the SRV actuator functional test for the two-stage SRVs. The section then states that the three-stage SRV actuator will be tested in the same manner. With respect to the three-stage SRVs, please describe the test methodology to be used for testing the three stage actuator. Specifically address how the testing will ensure that the actuator stem will engage and operate the second stage piston
Response
In the actuator functional test, for three-stage SRVs, the solenoid valve will be energized, the actuator will stroke, and the actuator stem travel will be measured in the space between the actuator and the SRV base. Stem movement will be measured using calibrated equipment and will be recorded in the test documentation package for future reference. To open the SRV, the actuator stem must move a minimum distance that includes a gap between the actuator stem and the second stage piston, and the required movement of the second stage piston to open the second stage disk. Since the actuator and piston stems are co-linear and are constrained to remain in alignment by the piston bore, there is no concern that the actuator will miss the second stage piston. Therefore, measuring the actuator stem travel and verifying that it moves the minimum distance described above, provides an acceptable means of verifying that the second stage piston is operating as required.