ML20141B956
| ML20141B956 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/26/1986 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| 0413V, 413V, GL-83-28, GN-846, NUDOCS 8604070155 | |
| Download: ML20141B956 (3) | |
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Georgia Fower Company Povta 2, Box 299A Wayrmbcro, Georgia 3083G Telcohone 4GS r.54 9931 304 724 8114 Sou*herri Company Servicer. Mc PoM OfNe Ocs 2t'25 L
Bem nghart, Atahma 35200 wnone us ""
Vogtle Project March 26, 1986 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Mr. B. J. Youngblood Log:
GF-846 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 REF:
GN-613, BAILEY TO DENTON, 5/20/85 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM 5: GENERIC LETTER 83-28
Dear Mr. Denton:
In the referenced letter commitments were made to review the VEGP Technical Specifications to ensure that post maintenance testing, as required by the Technical Specifications, did not degrade safety-related components. Attached for your staff's review are the measures taken to ensure that paragraphs 3.1 and 3.2 of GL 83-28 were considered in the preparation of the Technical Specifications.
If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, J. A. Bailey Project Licensing Manager JAB /sm Attachment xc:
R. E. Conway G. Bockhold, Jr.
R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2)
L. T. Gucwa B. Jones (Esquire)
Vogtle Project File l ptfS h I 'l 0413V 8604070155 060326 PDR ADOCK 05000424 E
PDR I
ATTACHMENT Generic Letter 33-28 3.1.3.
Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety.
Appropriate changes to these test requirements, with supporting justifica"f on, shall be submitted for staff approval.
(Note that action 4.5 discusses on-line system functional testing.)
Response: The VEGP Unit 1 Draft Technical Specifications which were submitted for review on February 28,1986 (Reference GN-821) incorporate the results of WCAP 10271, Supplement 1 " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Protection Instrumentation System."
The impetus for this study was the effect on the plant and plant personnel that nas been experienced during test and maintenance activities. Operating plants have experienced many inadvertent reactor trips during performance of surveillance, causing unnecessary transients and challenges to safety systems.
Significant time and effort on the part of the operating staff must -
be devoted to performing, reviewing, documenting and tracking the various surveillance activities, which in many instances seems unwarranted based on the high reliability of the equipment.
Significant benefits for operating plants appears to be achievable through revision of test and maintenance requirements.
WCAP 10271, Supplement i does not, however, address testing of the reactor trip breakers. A separate study is being conducted by Westinghouse under the direction of the Owner's Group to address this question. We plan to evaluate the results of this study for applicability to the VEGP Unit 1 Technical Specifications when the results become available.
3.2.3.
Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which are perceived to degrade rather than enhance safety.
Appropriate changes to these test requirements, with support justification, shall be submitted for staff approval.
Responset WCAP 10271, Supplement 2 applies the same methodology to the ESFAS which was applied to the RPS. This supplement to WCAP 10271 has been submitted to the NRC for review and we are in the process of evaluating the results for applicability to the VEGP Unit 1 Technical Specifications.
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In addition, we are developing a Turbine Overspeed Protection Reliability Program which will consist of a comprehensive program for turbine inspection and the maintenance, calibration, and testing of the -
turbine overspeed protection system. See the response to Question 430.50 for further discussion.
Finally, in our February 28, 1986 submittal of Draft Technical Specifications for VEGP Unit 1, we are proposing surveillance requirements for tile emergency diesel generators which are designed to reduce the frequency of cold fast starts and fast loading and improve emergency diesel generator reliability.
0413V i
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