ML17201M274
| ML17201M274 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/03/1989 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17201M272 | List: |
| References | |
| 50-237-88-10, 50-249-88-10, NUDOCS 8901090202 | |
| Download: ML17201M274 (2) | |
Text
- ~
- i.
- NOTICE OF VIOLATION Corranonwealth Edison Company Dresden Nuclear Station Docket No. 50-237 Docket No. 50-249 As a result of the inspection conducted during April 18-22, May 11-13, August 15, and December 13, 1988, and in accordance with the "General Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988),
the following violations were identified:
- 1.
Section III.L of Appendix R to 10 CFR Part 50 requires that alternate shutdown capability provided for a specific fire area shall be capable of maintaining the reactor coolant level above the top of the core.
In addition, supporting functions shall be capable of providing the process cooling lubric~tion, etc., necessary to permit the operation of the equipment used for safe shutdown functions.
Further,Section III.L requires that procedures shall be in effect to implement this capability.
The licensee was required to establish these procedures by July 19, 1985.
Contrary to the above, during the inspection conducted on April 18-22, 1988, an NRC inspector identified that no administrative procedures or controls were in effect to insure that required alternative shutdown equipment (i.e., control rod drive pump, service water pump, 4Kv Bus,
-480 Bus and 480V MCC) was available for the operating unit when the opposite unit (which houses the alternative shutdown equipment) wr.s in an outage or shutdown and the*required alternate shutdown equipment was removed from service for scheduled -maintenance or repair.
This is a Severity Level IV violation (Supplement IJ.
I
- 2.
10 *cFR 50.48(a) r'equires that each operating nuclear power plant h*ave a fire protection plan that satisfies Criterion 3 of Appendix A to 10 CFR Part 50.
It further requires that the plan.shall describe specific features necessary to implement the program such as administrative controls and the means to limit fire damage to structures, systems, or components important to safety so that the capability to safely shutdown the plant is ensured.
Section B.2 of the licensee's response to the Guidelines of Appendix A to APCSB 9.5-1 as accepted in the 1980 Supplemental Safety Evaluation Report indicates that effective administrative measures will be implemented to prohibit bulk storage of combustible materials inside or adjacent to saf~ty-related buildings or systems during operation or maintenance periods.
Contrary to the above, during a previous inspection conducted on April 12, 1988, an NRC inspector observed twenty 55-gallon drums of lubricating oil stored in a safety-related area on Elevation 517' - 6" (jn the southwest corner) of the Unit 2 Reactor Building. This condition existed from March 31 to April 13, 1988.
~
8901090~0~ ~_190103 I
F::-.*'DR
- Ar~,;-_.:.,c-.*~.*.*
c::- -
r (J._1(_)(1(1:2:"::7 Pru::*
~-:--.,~-::--:-.~~**'*
~"-'!
This is a Severity Level IV violation (Supplement I).
With respect to Item 1, the inspection showed that action had been taken to correct the identified violation and to prevent recurrence.
Consequently, no reply to this violation is required and we have no further questions regarding this matter.
With respect to Item 2, pursuaQt to the provision of 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice a written statement or explanation in reply, including for this violation:
(1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.*
Dated Aubert J. Miller, Director Division of Reactor Safety
~;.... - -.,. -
~,_.--
~..... -
,..,_._ -~-- -,...,,.. --- ----* -