ML18092A680
| ML18092A680 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/26/1985 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18092A679 | List: |
| References | |
| 50-272-85-01, 50-272-85-1, 50-311-85-04, 50-311-85-4, NUDOCS 8508050211 | |
| Download: ML18092A680 (2) | |
Text
APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Generating Station Units 1 and 2 Docket Nos. 50-272 and 50-311 License Nos. DPR-70 and DPR-75 As a result of the inspection conducted on January 21-25 and February 4-7, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), the following violation was identified:
Techni ca 1 Specification 6. 8 states that...
11written procedures sha 11 be esta-blished... covering... the applicable procedures recommended in Appendix A of Regulatory Guide 1.33...
11
- Regulatory Guide 1.33, Revision 2, February 1978, Appendix A, Item 6.a. recommends procedures for combating emergencies and other significant events including...
11 Loss of Coolant (including significant PWR steam generator leaks) (inside and outside primary containment) (large and small, including leak-rate determination).
11 Contrary to the above, during the inspection and review of Salem Unit 1 Reactor Coolant System (RCS) Leak Rate determinations made in November and December of 1984, Procedure SP(O) 4.4.6.2(d), RCS Water Inventory Balance, was inadequately established in that: (1) leakage occurring outside the containment was neither classified as identified nor unidentified leakage; this hindered entry into the Limiting Condition for Operation for Technical Specification 3.4.6.2 for events where the 11 unclassified 11 leakage would have increased the unidentified leakage above 1.0 gallon per minute. (§2.3.1); (2) No temperature correction was made to account for changes in temperature; in one case reviewed, this led to a non-conservative unidentified leakage. (§2.4); (3) Use of inappro-priate i dent ifi ed 1 eakage va 1 ues into the Reactor Coo 1 ant Ora in Tank ( RCDT) led in one case reviewed to a non-conservative unidentified leakage. (§2.3.2);
and, (4) Either computer or manual calculations could be used to generate the test results, allowing selection of the more favorable result and frequent use of the less precise manual calculation. (§2.3.3).
This is a Severity Level IV Violation (Supplement I) applicable to DPR-70.
Since the same procedure is used for Unit 2, the violation is also applicable to DPR-75.
Temporary changes to Surveillance Procedure SP(O) 4. 4. 6. 2( d) were made prior to February 7, 1985 to include RCS intersystem leakage outside containment in the unidentified leakage total, to provide for entry into the Technical Speci-fication Action Statement should unidentified leakage exceed 1.0 gallons per minute, to ap~ly appropriate RCDT leakage values and to designate the computer calculation as the preferred method.
( 85080502118-50730 ----
PDR..
ADOCK 05000272 PDR OFFICIAL RECORD COPY IR SALEMI/85-0l&II/85 0004.0.d 07/26/85
Appendix A 5
Pursuant to the prov1s1ons of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit to this office within thirty days of the date of the 1 etter which transmitted this Notice, a written statement or ex-planation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending this re-sponse time.
OFFICIAL RECORD COPY IR SALEMI/85-0l&II/85 0004.1.0 07/26/85