ML20079P860
| ML20079P860 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/01/1991 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P864 | List: |
| References | |
| NUDOCS 9111140116 | |
| Download: ML20079P860 (4) | |
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UNITF 0 STATES j
= p, NUCLEAR REGULATORY COMMISSION s..../
. WASHINGTON, D. C,20655 g
,t-r ENTERGY OPERATIONS. INC.
DOCKET-NO.-50-382 MTERFORDSTEAMELECTRICSTATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-38 t
The Nuclear ~ Reg'ulatory Comission (the Commission) has found that:
A.
TheLapplication for amendment by Entergy Operations Inc.
. (the ilicensee)-dated September 25, 1991, compliesWIththe standards:and requirements of the Atomic Energy Act of 1954, as amended (the Act),-and the Comission's rules and' regulations set forth in 10 CFR Chapter I; B.
The facility will o)erate in conformity with-the application, the provisions of t1e Act, and the rules and reguiations of the Commission; C.-
There -is reasonable assurance (1)_ th'at the activities authorized by this amendment can be conducted withoJt. endangering the health and safety of the public, and (ii):that such activities will be conducted in co@liance with the Comission's regulations; D._
.The issuance ~of this amendment will not be inimical to the common defense and security _or to-the health and safety of the
_public; and E.
The issuance of this amendment is-in accordance with 10 CFR Part 51. of. the Comission's-regulations and all-applicable requirements have been satisfied.
1 9111140116 911101 DR-ADOCK 0500 g2
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachn.ent to this license amendment, and paragraph 2.C(2) of facility Operating License No.
NPF-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 71, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
& j' N&
John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects 111, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 1, 1991 e
ATTACHMENT TO LICENSE t,MENDMENT NO. 71 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following p' age of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGE_
INSERT PAGE 3/4 8-7 3/4 8-7 e
f e
m TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE NUMBER OF FAILVRES IN NUMBER OF FAILVRES IN LAST 20 VALID TESTS.*,#
LAST 100 VALID TESTS
- TEST FREQUENCY ***
l 11 54 At least once per 31 days 12 15 At least once per 7 days **
- Criteria for determining number of failures and number of valid tests shall be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1, August 1977, where the last 20 and 100 tests are determined on a per diesel generator basis.
For the purposes of this test schedule, only valid tests conducted after the Operating License issuance date shall be included in the computation of the "last 100 valid tests".
Entry into this test schedule shall be made at the 31 day test frequency.
Increased test frequency for one diesel generator shall not affect the test frequency for the remaining diesel generator, even under the STAGGERED TEST BASIS criteria.
- This test frequency shall be maintained until seven consecutive failure-free demands have been performed and the number of failures in the last 20 valid demands has been reduced to one.
- For purposes of determining the required test frequency, the previous test failure count may be reduced to zero if a complet.e diesel overhaul to like-new conditions is completed, prov'ded that the overhaul, including appropriate post-maintenance operation and testing, is specifically approved by the manufacturer and if acceptable reliability has been demonstrated.
The reliability criterion shall be successful completion of 14 consecutive tests in a single series; 10 of these tests shall be in accordance with Surveillance Requirement 4.8.1.1.2a.4,5 and 4 of these tests shall include the fast loading requirement described in the double-asterisked (**N. note to surveillance requirement 4.8.1.1.2a.5.
If this criterion is not satis-fied during the first series of tests, any alternate criterion used to -
trans-value the failure count to zero may only be implemented with prior approval by the NRC.
- The valid failure to start the "A" Train Diesel Generator on 08/20/91 due to the loss of the power dropping resistor in the governor circuitry is not to be ccunted toward the adjustment of test frequency for the "A" Train EDG, If the first 14-valid tests on the "A" Train EDG following the 08/20/91 failure do not result in a failure caused by the new power dropping resistor, the valid 08/20/91 failure is trans-valued to zero and this provision no longer applies.
WATERFORD - UNIT 3 3/4 8-7 AMENDMENT NO. 23,71
__g TABLE 4.8 la ADDITIONAL ret 1 ABILITY AC110NS No. of failures No. of failures in last 20 in last 100 valid tests-
. valid tests Action 3
6 Within 14 days prepare and maintain a report for NRC audit describir:0 the diesel-generator-reliability improvement program implemented at the site.(see Note 1).
5 11 Declare the diesel generator inoperable.
Perform a requali-fication test program for the affected diesel generator (see Note 2).
e S
WATERFORD - UNIT 3 3/4 8-7a AMENDMENT NO.- 23
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