ML18011A391
| ML18011A391 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/09/1994 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18011A390 | List: |
| References | |
| 50-400-94-05, 50-400-94-5, NUDOCS 9403150196 | |
| Download: ML18011A391 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Carolina Power and Light Company Shearon Harris Unit 1
Docket No.:
50-400 License No.:
NPF-63 During an NRC inspection conducted on January 15 - February 18,
- 1994, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, the violations are listed below:
A.
Technical Specification 6.8. l.a. requires that written procedures be established and implemented covering procedures outlined in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Regulatory Guide 1.33, Appendix A, paragraphs 3, 6, and 9, require procedures for operation of the chemical and volume control system, for combating acts of nature, and for performing maintenance.
Operating Procedure OP-107, Chemical and Volume Control System, Section
- 8. 11,'pecifies that the bypass valve be closed after the reactor coolant filter is backflushed and filter inlet and outlet valves have been opened.
Administrative Procedure AP-301, Adverse Weather Operation, Revision 2, step 5.1.1.4.c.
directs operators to verify heaters are operable in all buildings and structures.
Haintenance Procedure EM-003, Termination and Testing of Wire and Cable, Attachment 1, specifies that cable conductors be properly identified and that'a quality verification check be performed.
Contrary to the above, l.
On February 18, 1994, the bypass valve for the reactor coolant filter was closed prior to the opening of the filter inlet and outlet valves.
This action resulted in the inadvertent isolation of the letdown system which challenged system relief valves.
2.
3.
As of January 19, 1994, following several periods during which Procedure AP-301 was in effect, several inoperable heaters in the emergency service water and emergency diesel generator structures were not identified.
This contributed to below design temperatures existing in both areas during a recent winter cold spell.
On January 7,
1994, cable conductors were not properly identified for motor operated valve AV-B4 which resulted in valve operation in the opposite direction during functional testing.
In addition a quality verification check for these conductors was not properly performed.
This is a Severity Level IV violation (Supplement I).
9403l,50196 940309
,PDR ADOCK 05000400 0
'P C
Carolina Power and Light Company Shearon Harris Unit 1
Docket No.:
50-400 License No.:
NPF-63 B.
10 CFR 50, Appendix 8, Criterion XVI, states that measures shall be established to assure conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and non-conformances are promptly identified and corrected.
The licensees Corporate guality Assurance
- Manual, paragraph 12.3, requires that significant conditions adverse to quality be documented and reported to management.
- Further, the manual requires that corrective actions be determined which will preclude repetition of the condition.
Contrary to the above, As of February 18, 1994, corrective actions regarding temperature maintenance of boron injection system flowpaths, were not adequate to prevent the boric acid transfer pump valve gallery room temperature from falling below the 65'F minimum requirement in technical specification 3.1.2.2.
2.
Corrective actions taken in response to LER 92-02, dated January 19,
- 1992, were insufficient to identify and correct a
degraded function of the plant computer for the Safety Parameter Display System on February 17, 1994.
This resulted in the failure to declare an Unusual Event for approximately two days.
This is a Severity Level IV Violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit a written statement or explanation to the U. S.
Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, D.
C.
20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results
- achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this Notice, an order or demand for information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this 9th day of March 1994