ML18010A468
| ML18010A468 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/27/1991 |
| From: | Verrelli D NRC Office of Inspection & Enforcement (IE Region II) |
| To: | |
| Shared Package | |
| ML18010A467 | List: |
| References | |
| 50-400-91-24, NUDOCS 9112120130 | |
| Download: ML18010A468 (4) | |
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 October 19 -
November 15,
- 1991, 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 (1991), the violations are listed below:
A.
TS 4.0.5 requires that inservice testing of pumps shall be in accordance with Section XI of the American Society of Mechani'cal Engineers (ASME)
Boiler and Pressure Vessel Code.
ASME Section XI, Subsection IGP, Inservice testing of Pumps in Nuclear Power
- Plants, Section IGP 3230.(a),
requires that the testing frequency shall be doubled until the cause of the deviation is determined or corrected.
Contrary to the above, the boric acid pump shutdown quarterly testing frequency was not doubled as required for previously identified pump degradation.
Therefore, subsequent to successful testing on March 16,
- 1991, the boric acid pumps were not tested six weeks later during a plant shutdown to cold shutdown in May 1991.
This is a Severity Level IV violation (Supplement I).
B.
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, paragraph 8.b requires procedures for the conduct of surveillance tests.
Contrary to the
- above, surveillance procedure OST-1021, Daily Surveillance Requirements, which implemented the requirements of TS 4.1.2.l.a and 4.1.2.2.a, was not adequate in that it did not properly verify that the emergency boration flowpath was maintained greater than 65 degrees F.
This is a Severity Level IV violation (Supplement I).
r C.
10 CFR 50, Appendix B, 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.
9112120130 911127 PDR ADOCK 05000400 8
Carolina Power and Light Company Shearon Harris Unit 1
Docket No. 50-400 License No. NPF-63 The licensee's Corporate guality Assurance
- Manual, paragraph 12.3. 1, further requires that personnel are responsible for reporting conditions adverse to quality, discovered as a result of inspections, observations, surveillance, assessments, monitoring, audits, tests,
- checks, and review of documents.
Alarm response procedure APP-ill, Freeze Protection and Temperature Maintenance, Sections ALB 111-8-4, HT-18753 B
RAB Trouble, and ALB 111-8-5, HT-18753, C
RAB Trouble, action 2.f, requires the operator to initiate a work request to correct an indicated problem.
Contrary to the above, measures were not taken to assure that conditions adverse to quality were promptly identified and corrected in that multiple alarms were received on heat trace alarm panels HT-18753 B and HT-18753 C and operations failed to initiate work requests as required by action 2.f of the alarm response procedure.
This is a Severity Level IV violation (Supplement I).
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 if applicable, a
copy to the NRC Resident Inspector, 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 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.
Where good cause is
- shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION David M. Verrelli, Chief Reactor Projects Branch 1
Division of Reactor Projects Dated at Atlanta, Georgia this 27 day of November 1991