ML18033B196
| ML18033B196 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/02/1990 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18033B195 | List: |
| References | |
| 50-259-89-43, 50-260-89-43, 50-296-89-43, NUDOCS 9003130024 | |
| Download: ML18033B196 (7) | |
Text
NOTICE OF VIOLATION Tennessee Valley Authority Browns Ferry Units 1, 2, and 3
Docket Nos.
50-259, 50-260, and 50-296 License Nos.
DPR-33, DPR-52, and DPR-68 EA 89-226 During the Nuclear Regulatory Commission (NRC) inspection conducted on September 11 - October 11, 1989, four violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violations are set forth below:
A.
Technical Specification (TS) 6.8. 1, Procedures, requires in part, that written procedures be established, implemented and maintained covering surveillance and test activities of safety-related systems.
Contrary to the above, 1.
On, August 15, 1989, the licensee failed to adequately establish and implement surveillance procedure O-SI-4.2.B-67, Residual Heat Removal (RHR) Service Water Initiation Logic.
Specifically, the surveillance test was inadequate in that it jumpered out the automatic initiation logic for all Emergency Equipment Cooling Mater (EECM) pumps.
This was inappropriate to the circumstances because all eight of the Emergency Diesel Generators, as well as other safety-related equipment that require automatic initiation of EECM cooling water to function, were rendered inoperable.
2.
On December 9, 1988, during performance of 2-SI-4.2B-45A (I),
RHR Logic System Functional Test, the operator failed to follow the procedure step requiring depression of the local manual stop button and instead, depressed the pump start button.
This resulted in the startup of the 2D RHR pump.
3.
On December 17, 1988, during the performance of O-SI-4.9.A. 1.b-1, Unit 1/2 DG A Load Acceptance
- Test, the operator failed to follow the correct sequence of steps in the procedure.
Steps which initiate the pump start logic were performed prior to steps intended to block the automatic start signal.
This resulted in the startup of the 2D RHR pump.
9003130024 900302 PDR ADOCK 05000259 IJ PDC
0 Notice of Violation 4.
On December 18, 1988, during the performance of O-SI-4.9.A.l.b-2, Unit 1/2 DG B Emergency Load Acceptance
- Test, the operator placea the wrong keylock switch in the test position.
This resulted in the szartup of the 2C Core Spray pump during subsequent steps in the procedure.
B.
Technical Specification 4.9.A.l.e requires that a sample of diesel fuel be checked for quality once a month.
Contrary to the above, from June 6 unti 1 September 12, 1989, the licensee failed to check the quality of the diesel fuel in all storage tanks once per month.
Procedure O-SI-4.9.A.l.e, Diesel Generator Fuel Oil Analysis, which was reviewed and validated on June 6, 1989 in accordance with Site Director Standara Practice 7.4, was deficient in that it required only one of the four sets of seven-day storage, tanks to be sample checked each month on a staggered basis.
Consequently, each tank was sampled only once per four months.
C.
Technical Specification 3.11.E.l.a requires, in part, that with one or more of the fire hose stations shown in Table 3.11.C inoperable, provide a
gated wye on the nearest operable hose station, with one outlet connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station.
Contrary to the above, on September 19, 1989, the gated wye and associated length of hose installed at 565 U-R9 (2-26-861) on June 28, 1989, to provide coverage for the areas left unprotected by inoperable hose stations 565 U-R13 (2-26-878) and 541 P-R14 (2-26-877) referenced in Table 3.11.C, were missing.
These violations are considered in the aggregate as a Severity Level III Violation (Supplement I) applicable to all three units.
Pursuant to the provisions, of 10 CFR 2.201, the Tennessee Valley Authority is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC
- 20555, with a copy to the Associate Director for Special Projects, Office of Nuclear Reactor Regulation, and a copy to the NRC Resident Inspector, Browns Ferry, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) admission or denial of the violation, (2) the reasons for the violation if admitted, (3) the corrective steps which have been taken and the results
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should
Notice of Violation not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
Consideration may be given to extending the response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION Oated at Rockville, Maryland this 2nd day of March 1990
'Y.
Oennis M. Crutch ield, Ass ciate D>rector for Special Projects Office of Nuclear Reactor Regulation
Nr. Oliver D. Kingsley, Jr.
March 2, 1990 DISTRIBUTION:
PDR SECY CA
- THurley, NRR
- FIngram, PA
- BHayes, OI
- EJordan, AEOD DWi'1 1iams, IG WTroskoski, OE Docket Files Projects Reading ADSP Reading BWilson, RII WLittle, RII
- KIvey, Resident Inspector OE:EA File OE:Day File
- BSummers, OE (ltr hd)
DCS BDLiaw SBlack RPierson TRoss ADSP Reading OE &~i WTros kos ki 2/go/90
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NRR/
P DCrutchfie 1 d 2/Zg/90 DED berman HTho pson 2/y/90 2/
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