ML20034B868
| ML20034B868 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/20/1990 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20034B866 | List: |
| References | |
| 50-219-90-06, NUDOCS 9005010094 | |
| Download: ML20034B868 (2) | |
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V o-4 APPENDIX A NOTICE OF VIOLATION GPU Nuclear Corporation Docket No 50-219 Oyster Creek Nuclear Generating Station License No. DPR-16 q
During an inspection conducted February 18 - March 17, 1990, and in-accordance with the " General Statement cf Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, 1990 the following violations were. identified::
i A.
Technical Specification 3.2.B.2 requires "The Rod Worth Minimizer (RWM) l-shall be operable during each reactor startup until reactor power reaches 10% of rated power." "Should the RWM be. inoperable before a startup is commenced or before the first twelve rods are withdrawn, one startup during each calendar year may be performed without the RWM provided that the~
second licensed operator verifies that the-licensed-. operator at the reac-
'l tor console is following the rod program and provided that a reactor engi-I neer from the Core Engineering Group also verifies that the rod progre. is i
-being followed."
l Contrary to the above, the rod worth minimizer was not in service on February 15, 1990, when a reactor startup was initiated and seven control rods were' withdrawn. Additionally, neither.a-second licensed operator nor i
a reactor engineer were stationed with the purpose to. verify that the rod program was being followed.
This violation is severity level IV (Supplement IV).
j B.
. Technical Specification 6.11 requires that procedures for personnel radi--
-i ation protection be prepared consistent with the requirements of 10 CFR 20, and be approved, maintained and adhered to for all operations involv-ing personnel radiation exposure.
Plant Procedure 9300-ADM-4000.11, " Rules for Conduct of Radiological Work," and Procedure 9300-ADM-4010.2, "ALARA Review Procedure," require the department initiating work to coordinate an ALARA review. The proce-dures further require that radiological engineering will perform-an ALARA review for any task anticipated to accumulate 5 person-rem or more of total exposure.
Contrary to the above, from about February 6, 1990, through February 15,-
1990, while performing maintenance on the'"A" reactor recirculation pump under Job Order No. 21359, the pump bearing was removed, measurements l
taken, and the bearing was replaced without this scope of the work receiv-ing the required ALARA review. This scope of work resulted in approxi-
~,
mately 11 person-rem of exposure.
This violation is severity level IV (Supplement IV).
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. Appendix A 2-C.
. Technical Specification 3.12.C.1 requiresifire protection sprayL and/or L
sprinkler systems listed in Table. 3.12.2 be operable. Table 3.12.2 speci-
'fies. operability'of deluge systems 4A and 4B for'the cable spreading room r
(firearea08-FC-4).
Technical Specification 3.12.C.2 requires that when one or more of thez above. required spray and/or sprinkler systems are inope'rable,. the licensee establish a continuous fire watch, with backup fire suppression equipment,-
for those areas..in which redundant systems. or components could: be damaged.-
Contrary to the above, from January 23, 1990, until February 8,1990, fire' suppression deluge system 4A was inoperable'in-the cable spreading room which is an area containing redundant components,-and a continuous: fire-watch was not established.
This violation-_is seo rity level IV (Supplement I).
D.
Technical Specification 6.8.1 requires that written procedures be estab-11shed, implemented'and maintained _that meet or-exceed Regulatory. Guide 1.33, Rev. 2.
Regulatory Guide 1.33, Rev. 2, endorses ANSI 18.7-1976, Section 5'.2.2, j
which requires that procedures be followed.
L Station Procedure 106.2.1,." Spill Procedure," requires that, if the event has contaminated a nonradioactive system, further use of the: system'shall be restricted until the cause of the. contamination is identified and cor-l rected, and the system has been decontaminated.
If-it_is necessary.to continue operation of the system as contaminated, the procedure requires an immediate. safety evaluation to be performed in accordance vith the re-quirements of 10 CFR 50.59.
Contrary to the above, on February 17, 1990, a spill from the No. 2 auxili-ary boiler occurred which was identified to be radioactive.
Further use of the normally nonradioactive Auxiliary Boiler System was not restricted, the cause of the contamination was not corrected, and the system was not i
decontaminated. A.:afety evaluation in accordance with the requirements of 10 CFR 50.59 was not pr.' formed until March 22, 1990_to evaluate con-tinued operation. As a result-of this continued operation, another radio-active spill occurred on March 10, which resulted in a second unplanned release of radioactive material to the environment.
This is a Severity Level IV violation (Supplement I).
Pursuant to the prov1sions of 10 CFR 2.201, GPU Nuclear Corporation is hereby re-quirt.d to submit to this office within thirty days of the date of the letter which transmitted these Notices, a written statement or explanation in reply, including:
(1) corrective steps which have been taken and the results achieved, (2) correc-tive steps which will be taken to avoid further violations, and (3).the date when full compliance will be achieved. Where goad cause is shown,. consideration'will be given to extending this response time.
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