ML18005A264
| ML18005A264 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/29/1988 |
| From: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18005A263 | List: |
| References | |
| 50-400-87-40, NUDOCS 8802080261 | |
| Download: ML18005A264 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Carolina Power and Light Company Shearon Harris Docket No. 50-400 License No.
NPF-63 During the Nuclear Regulatory Commission (NRC) inspection conducted on September 24 -
October 27,
- 1987, and October 27 - November l2,
- 1987, four violations of NRC requirements were identified.
The violations involved inadequate corrective action, failure to follow procedure, and failure to take prompt corrective action on conditions adverse to quality.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1985), the violations are listed below:
A.
Technical Specification 6.8. la requires that written procedures be imple-mented covering the procedures outlined in Appendix A of Regulatory Guide 1; 33, Rev.
2, February 1978.
Administrative Procedures are identified in Appendix A of the Regulatory Guide.
An Administrative Procedure titled "Operations - Conduct of Operations" OMM-l, Rev.
3, Step 3. 2. 3. 4, requires the shift foreman to ensure the safe operation of the plant at all times.
Contrary to the
- above, on October 9, 1987 OMM-1 was not implemented, in that the shift foreman authorized control room operators to manipulate reactor coolant vent valves RC 900, RC-901, and RC-902 with the knowledge that operating these valves probably would cause the uncontrolled opening of RC-904 and RC-905'he vent valves were individually operated and in each instance RC-904 and RC-905
- opened, thus allowing a vent path for reactor coolant to flow into the containment atmosphere and into the pressurizer relief tank.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR 50, Appendix 8 Criterion
- XVI, FSAR Section 17.2.16 and CP8L Corporate Quality Assurance Program Section 15.2.5 collectively require that the licensee take prompt corrective action on conditions adverse to qual ity.
Contrary to the
- above, prompt corrective action on conditions adverse to quality was not taken in that, in June
- 1985, and February
- 1987, the licensee experienced spurious opening of Reactor Coolant Vent System valves during testing.
Both these problems are conditions adverse to quality and were not corrected until October
- 1987, whic'h resulted in a loss of reactor coolant inventory on October 9, 1987.
This is a Severity Level IV violation (Supplement I).
880208026i 880i29 PDR ADOCK 05000400 G
'Carolina Power and Light Company Shearon Harris Docket No.
50-400 License No.
NPF-63 C.
10 CFR 50, Appendix 8, Criterion
- XVI, FSAR Section 17.2.16 and CP8L Corporate Quality Assurance
- Program, Section 15.2.5 collectively require that corrective action be taken to preclude repetition of significant conditions adverse to quality.
Contrary to the
- above, the licensee failed to take adequate corrective action to preclude repetition, in that following the date for full corrective action to a vio'1ation of Technical Specification 3.6. 1.3.a on June 11, 1987, identified in NRC Inspection Report 50-400/87-21, licensee personnel'reached containment integrity on August 31, 1987 and again on September 17,
- 1987, resulting in both the inner and outer containment personnel access doors being opened at the same time, violating Technical Specification 3.6.1.3. a.
This is a Severity Level IV violations (Supplement I).
D.
Technical Specification 6.8. 1a requires that written procedures be established and implemented covering the procedures outlined in Appendix A of Regulatory Guide 1.33, Rev. 2, February 1978.
Operations Procedures are identified in Appendix A of the Regulatory Guide.
a.
Contrary to the
- above, procedures were not implemented, in that, on November 7,
- 1987, operations personnel failed to properly set the Steam Dump Control system as required by site Operations Procedure OP-126, Rev.
2, Hain Steam, Extraction Steam and Steam Dump System, subsequently -resulting in a reactor trip and safety injection.
b.
Contrary to the
- above, procedures were inadequately established in that OP-134, Rev.
2, Condensate
- System, did not stipulate that condenser recirculation isolation valve 1CE-293 be retur ned to its normal position, which resulted, on November 8, 1987, in operations personnel fai ling to reposition valve 1CE-293 to the proper position for power operations, thus subsequently requiring a manual trip of the reactor.
This is a Severity Level IY violation (Supplement I).
Pursuant to the provisions of 1Q CFR 2. 201, Carolina Power and Light Company 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 Regional Administrator, Region II, 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 reason 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.
Where good
Carolina Power and Light Company Shearon Harris Docket No. 50-400 License No.
NPF-63 cause is shown, consideration will be given to extending the response time.
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 not be modified suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION J ~ Nelson Grace Regional Administrator Dated at Atlanta, Georgia this 29th day of January 1988