ML18139B586
| ML18139B586 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/04/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139B583 | List: |
| References | |
| 50-280-81-22, 50-281-81-22, NUDOCS 8111050368 | |
| Download: ML18139B586 (3) | |
Text
APPENDIX A NOTICE OF VIOLATION Virginia Electric and Power Company Surry 1 and 2 Docket Nos. 50-280 & 50-281 License Nos. DPR-32 & DPR-37 As a result of the inspection conducted on June 1 - July 31, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7, 1980),
the following violations were identified.
A.
Technical Specification 3.7.B requires the minimum degree of redundancy of one be maintained for the overpower and overtemperature delta temperature protection system as provided in TS table 3.7.1 or the plant be placed in hot shutdown.
Contrary to the above, on July 9, 1981 the minimum degree of redundancy was reduced to zero for the overpower and overtemperature delta temperature protection systems.
Corrective action was initiated but erronously discontinued without returning the degree of redundancy to one by tripping the channel.
The condition was corrected about twelve hours later.
This is a Severity Level IV Violation (Supplement I.D.2.).
Criterion XVI of Appendix B to 10 CFR 50 and Section 16 of the VEPCO NPS QA Manual require that the identification of conditions adverse to quality, the cause of the condition, and the corrective action taken be documented and reported to appropriate levels of management.
Administrative Procedure ADM-29, Conduct of Operations, requires that the Shift Supervisor and Control Room Operator (CRO) Logs contain detailed information of any abnormal conditions or problem areas, noting the time, the reasons and the corrective action taken on these items.
Contrary to the above, on July 30, 1981, increasing Unit 2 reactor coolant system (RCS) leakage was identified on the midnight to 8:00 a.m. shift; however, the identification of this adverse condition, the cause, or the action taken to correct it was not documented in the Shift Supervisor or CRO logs, or on a Deviation Report, until 9:40 a.m. on July 30, 1981.
This is a Severity Level V Violation (Supplement I.E.), and applies to Unit
- 2.
C.
Criterion XIV of Appendix B to 10 CFR 50 and Section 14 of the VEPCO Nuclear Power Station QA Manual establish measures for indicating the operating status of structures, systems, equipment and components of the nuclear power station. Section 14 of the QA Manual, Part 5.2, requires that jumpers or
.temporary modifications including lifted electrical leads and electrical jumpers (wires), shall be properly controlled, documented, and approved, and sha 11 be insta 11 ed by an approved procedure or a 11Jumper Log 11 form.
8111050368 811016 PDR ADOCK 05000280 G
Virginia Electric & Power Company Notice of Violation 2
Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Contrary to the above, the control room annunciator alarm card IC-46, which contains electronics for the spent fuel pit high level alarm (CF6), was found pulled and inoperable without the proper controls, documentation, and approvals on June 3, 1981.
The inoperable alarm contributed to the spent fuel pit overflowing and an unplanned radioactive release from the station on June 3.
This is a Severity Level V Violation (Supplement I.E.)
D.
Technical Specification, Section 3.2.A, requires at least one flow path to the core for boric acid injection when fuel is in the reactor.
Contrary to the above, on June 12, 1981, Unit 1 did not have an operable flow path of borated water to the core with fuel in the reactor.
The low head and high head safety injection systems were isolated and inoperable, and the flow path from the Refueling ~Jater Storage Tank to the core through MOV-RH-100 was inoperable during cold shutdown conditions.
Motor operated valve (MOV)-RH-100 was closed and failed to open when tested at the request of the inspector. Additionally, the specific system alignment for the boric acid flow path was not addressed in facility procedures.
This is a Severity Level V Violation (Supplement I.E.).
E.
Technical Specification 6.4.A requires that detailed written procedures with appropriate check-off lists and instructions shall be provided for plant operation and for calibration and testing of instruments, components, and systems involving nuclear safety of the station.
F.
Contrary to the above, the calibration procedure for the CAT level instru-mentation (CAL-CS-005) was not appropriately revised prior to exceeding 350° F and 450 psig in the Unit 1 reactor coolant system on July 4, 1981, to reflect the density difference between pure water and the 17.5% (by weight) solution of sodium hydroxide in the CAT.
When the density correction and recalibration was performed on July 4, 1981, the CAT level was at 82%, well below the minimum TS 3.4.A.4 level of 96.5%.
The is a Severity Level V Violation (Supplement I. E.)
Technical Specification 4.1.A requires reactor containment pressure instrumentation and consequence limiting safeguards (CLS) systems to be tested monthly or prior to exceeding 350° For 450 psig in the reactor coolant system.
Contrary to the above, the Periodic Test for CLS HI-HI containment pressure trains, were not performed during the Unit 1 steam generator replacement outage nor prior to exceeding 350° F and 450 psig in the Unit 1 reactor coolant system on July 4, 1981.
An operability test was last performed on August 16, 1980, suspended during the outage, and subsequently performed on July 8, 1981, following inspector discussions with Licensee management.
This is a Severity Level V Violation (Supplement I.E.).
e Virginia Electric & Power Company e
Docket Nos. 50-280 and 50-281 3
Notice of Violation License Nos. DPR-32 and DPR-37 Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) admission or denial of the alleged viola-tions; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
The responses directed by this Notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.
SEP 4 1981 Date: -------
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