05000272/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl

Forwards LER 81-040/03L-0.Detailed Event Analysis Encl

ML18086A554
Person / Time
Site:	Salem
Issue date:	05/15/1981
From:	Uderitz R Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18086A555	List: 05000272/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl 05000272/LER-1981-040-03, /03L-0:on 810220,records of Completed Surveillance Tests Found Missing.Caused by Faulty Procedures Not Providing for Permanent Storage of Records.Firmer Controls Will Be Established for Record Transmittal
References
NUDOCS 8105270342
Download: ML18086A554 (3)

LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2721981040R00 - NRC Website

text

Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 Mr. Boyce H. Grier Director of USNRC May 15, 1981 Off ice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 81-40/03L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence Bl-40/03L.

The lateness of this report is due to the extensive investigation involved in determining procedural defects following receipt of the final Quality Assurance reports and Corrective Action Request.

Sincerely yours,

.1'l£ t4~;r R. A. Uder1 tz' General Manager -

Nuclear Production CC:

Director, Office of Inspection and Enforcement (30 copies)

Director, Office of Management Information and Program Control (3 copies) a 1o5~~ tl0 ~~\\r Th.s ~ ne:*~iv Peor:>le

'3 95*2001 1350M1 4*8l:

Report Number:

Report Date:

Occurrence Date:

Facility:

81-40/03L May 15, 1981 2/20/81 Salem Generating Station, Unit 1 Public Service Electric & Gas Company Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Missed Surveillance CONDITIONS PRIOR TO OCCURRENCE:

• Various Operational Modes DESCRIPTION OF OCCURRENCE:

Station Quality Assurance Audit 80-4-C.l-2, completed on February 20, 1981, discovered that records of completed surveillance tests could not be located for the following Technical Specification require-ments.

1.

Technical Specification 4.3.3.6.2, Fire Detection Instruments Table 3.3-10, Item 9, Fuel Handling Building 269, no records could be located to verify that these circuits had ever been tested.

2.

Technical Specification 4.4.6.2.b, Reactor Coolant Leak Detection, documentation could not be located for the following dates:

July 12, 1980 July 24, 1980 August 4, 1980

3.

Technical Specification 4.4.6.2.c, Controlled Leakage Data, documentation could not be located for the month of August 1980.

4.

Technical Specification 4.8.Ll.2, Electrical Power Systems -

Emergency Diesels, documentation could not be located for Diesel lC for the month of June 1980.

Each lack of documentation noted above constituted operation in a degraded mode IAW Technical Specification 6.9.1.9.b.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Pr~cedural In~dequacy. Existing procedures lack the necessary guidance required by control room personnel to maintain firm control of log sheets and surveillance test check-of£ sheets prior to being permanently stored.

1 " --

~ER 81-40/03L 2

5/15/81 Appendix "M" {Smoke and Thermal Circuit Operable Test) of the ~ire Fighting and Organizational Manual is used to doc~ent c~mp~etion of Technical Specification 4.3.3.6.2.

The Fuel Handling Building vent equipment room and the electrical control area {Zone 69) are not included in this procedure.

ANALYSIS OF OCCURRENCE:

Technical Specification 4.3.3.6.2 requires the circuits between the detection instruments and the control room shall be demon-strated operable at least once per 92 days per approved procedures.

Technical Specification 4.4.6.2.b requires that Reactor Coolant System leakages shall be demonstrated to be within the limits stipulated by Limiting Condition for Operation 3.4.6.2 by monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Technical Specification 4.4.6.2.c requires that Reactor Coolant System leakages shall be demonstrated to be within the limits stipulated by Limiting Condition for Operation 3.4.6.2 by measure-ment of controlled leakage from the Reactor Coolant Pump Seals at least once per 31 days when the Reactor Coolant System pressure is 2230 + 20 psig and valve 1CV71 is fully closed.

Technical Specification 4.8.1.1.2 requires that each diesel generator shall be demonstrated operable at least once per 31 days on a staggered test basis:

by verifying the fuel level in its day tank; verifying the diesel starts from ambient condition and accelerates to at least 900 rpm in < 10 seconds; verifying the generator is synchronized, loaded to > 1400 kw, and operabes for ~ 60 minutes; and verifying the diesel generator is aligned to provide standby power to the associated vital busses.

CORRECTIVE ACTION

An Operating Memorandum is being written which will provide guidance to control room personnel in order to establish firmer control of log sheets and surveillance test check-off sheets prior to being permanently stored.

On-the-Spot Change P-1 has been generated to include Zone 69 in the surveillance requirement of Appendix M of the Fire Fighting and Organizational Manual.

This change will apply to Units Nos.

1 and 2.

Zone 69 was tested satisfactory on February 20, 1981, the date On-the-Spot Change P-1 became effective FAILURE DATA:

Not Applicable Prepared By W. J. Steele SORC Meeting No.

81-34 Managi<<" -

Salem ~rating Station