ML18142A204
| ML18142A204 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/22/1985 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18142A201 | List: |
| References | |
| 50-281-84-34, NUDOCS 8503140310 | |
| Download: ML18142A204 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Virginia Electric and Power Company Surry Unit 2 Docket No. 50-281 License No. DPR-37 The following violations were identified during an inspection conducted on November 5 - 30, 1984.
The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).
Technical Specification 6.4.B requires that detailed written procedures with appropriate check-off lists and instructions be provided for normal startup, operation, and shutdown of a unit, and for all systems and components involving operation and shutdown of a unit, and for all systems and components involving nuclear safety of the station, including actions to be taken for specific and foreseen malfunctions of systems or components~
including alarms, shall be followed.
Contrary to the above, the following operating and administrative procedures were not.properly followed during the Unit 2 restart to full power opera-tion:
- 1.
Operating Procedure OP-lA, Startup Checklist, requires the signature (permission) of the Superintendent of Operations before exceeding three startup hold points; prior to exceeding 200°F, prior to raising the plant temperature and pressure above 350° and 450 psig, and prior to criticality and power operations.
In addition, identified systems which undergo significant maintenance during the outage are listed at these hold points to ensure adequate valve checklists are performed.
Contrary to the above requirements, only the final hold point (criticality and power operation) was properly signed off via tele-communications with the Superintendent of Operations, and no valve checklists were listed at any of the three OP-lA hold points, although Unit 2 was shutdown for approximately three weeks during replacement of the 11A 11 reactor coolant pump motor and seals.
Engineered Safeguards and Reactor Coolant System (RCS) checklists were performed as detailed in the Shift Order Book.
The Unit 2 reactor tripped from 20 percent power on November 20, 1984, due to a low water level condition in the 11C 11 steam generator. The manual isolation valves (2-FW-16, 47, and 78) in the main feedwater lines were found closed, and manual isolation valve 2-FW-85 in the feedwater bypass line was partially (75%) closed.
- 2.
Administrative Procedure ADM-29.3, Operation Department Logs and Records, requires the logging of annunciator alarms which extend beyond shift change, require maintenance, or have safety significance, in the Annunciator Logbook.
In addition, ADM-29.3 requires a weekly review of the Annunciator Logbook by management personnel.
8503140310 850307 I PDR ADOCK 05000280 G
Virginia Electric and Power Company Surry Unit 2 2
Docket No. 50-281 License No. DPR-37 Contrary to the above requirements, fifteen control room safety-related alarms were annunciated during and subsequent to the Unit 2 restart without being properly logged in the Annunciator Logbook.
In addition, the 1 ogbook review was documented on November 13, and November 26, 1984, and not during the week of the restart when the alarms were outstandng.
The inspectors did verify that the operators were monitoring the alarms and initiating corrective actions on them, and that none of the alarms resulted in Technical Specification violations for equipment operability.
This is a Severity Level IV violation (Supplement I), and applies to Unit 2.
Pursuant to 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:
(1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective ~teps which have been taken and the results achieved; (4) corrective steps whH:h will be taken to avoid further violations; and (5) the date when full compliance will be achieved.
Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73. 21.
Date: JAtl221985