ML20028E097
| ML20028E097 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/07/1983 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028E096 | List: |
| References | |
| 50-293-82-29, NUDOCS 8301200343 | |
| Download: ML20028E097 (3) | |
Text
_ _ _ _
APPENDIX A NOTICE OF VIOLATION Boston Edison Company Docket No. 50-293 Pilgrim Nuclear Power Station License No. DPR-35 As a result of the inspection conducted on October 19, 1982 - November 15, 1982, and in accordance with the NRC Enforcement Policy (10 CFR Part 2 Appendix C) published in the Federal Register on March 9, 1982, (47 FR 9987), the following violations were identified:
A.
Technical Specification (T.S.) 6.8.A requires that written procedures be implemented that meet or exceed the requirements and recomendations of USNRC Regulatory Guide 1.33.
tagging) gulatory Guide 1.33 requires procedures Re for equipment control missionandclearance)(. and for the control of maintenance (per-Station procedure 1.4.5, PNPS Tagging Procedure, Revision 10, requires the authorization and logging of protective tags on a Maintenance Request in accordance with procedure 1.5.3, or in a Red Tag log (when maintenance is not involved).
Station procedure 1.5.3, Maintenance Requests, Revisions 14 and 15, require the Watch Engineer's signed pemission to start the isolation, and the logging of all protective devices being tagged.
Contrary to the above, between October 29, 1982 and November 10, 1982, written procedures for equipment control (tagging) and maintenance were not correctly implemented as evidenced by the following:
1 On October 29, 1982, a red tag was placed on the 125 v. dc control power for MOV 2301-3 during maintenance without logging this tag on the associated Maintenance Request (s).
On November 5,1982, the jockey fire pump was isolated (red tagged) for an active Maintenance Request (No. 82-1555) without the Watch Engineer's signed pennission to start the isolation.
On November 9,1982, the four Traversing Incore Probe machines were red tagged without an active Maintenance Request or entry in the Red Tag log, and On November 10, 1982, the High Pressure Coolant Injection (HPCI) system MOV 2301-3 125 v. de control power was red tagged without an entry in the red Tag log.
This is a Severity Level V violation (Supplement I).
8301200343 830107 PDR ADOCK 05000293 w?ICIAL EICOED COPJ
_.~ _ _ _- ---._. -
~
Appandix A 2
B.
Technical Specification 2.2 requires that the Main Steam Safety Valves be set to lift at 1240 psig 13 psi.
Station procedure 3.M.4-7, Main Steam Safety Valve, Revision 4, requires that when setting the safety valves with nitrogen, the original nitrogen test setting stamped on each indivi-dual nameplate should be used to assure a steam lifting pressure of 1240 psig 13 psi.
Contrary to the above, on February 15, 1982, the 'A' Main Steam Safety Valve was set with nitrogen to lift at 1240 psig (nominal steam lifting pressure) vice the nitrogen nameplate setting of 1170-1185 psig.
This is a Severity Level IV violation (Supplement I).
C.
10 CFR 50, Appendix B, Criterion VI, Document Control, requires that measures be established to control the issuance of documents affecting quality.
The Bnston Edison Company Operations Quality Assurance Manual, Section 2.3, dated June 15, 1981, states that the Q-List is a list of safety related systems, structures, and components, and is issued in a controlled manner.
Contrary to the above, on October 12, 1982 the Nuclear Operations Support Department (Records Management Group) distributed an October 8, 1982 revision to the Q-List without establishing measures to properly control issuance of this revision to control copy holders of the Q-List.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Boston Edison Company is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, in-cluding the following information:
(1) the corrective steps which have been taken and the results achieved for Items A and C; (2) the corrective steps which will be taken to avoid further violations for all Items; and (3) the date when full compliance will be achieved for Items A and C.
Where good cause is shown, consideration will be given to extending this response time.
l l
i e
l l
l OFFICIAL RECCRD CCFY
APPENDIX B NOTICE OF VIOLATION Boston Edison Company Docket No. 50-293 Pilgrim Nuclear Power Station License No. DPR-35 As a result of the inspection conducted on October 19, 1982 - November 15, 1982, and in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C) published in the Federal Register on March 9, 1982 (47 FR 9987), the following violations were identified:
THIS PAGE, CONTAINING SAFEGUARDS INFORMATION, NOT FOR PUBLIC DISCLOSURE, IS INTENTIONALLY LEFT BLANK I
i 0FFICIAL EECORD COPY l
._