IR 05000324/1978020

Insp Repts 50-324/78-20 & 50-325/78-20 on 780815-18.No Noncompliance Noted.Major Areas Inspected:Lers,Ie Bulletins & Circulars & Followup of Open Items

ML20062B869
Person / Time
Site:	Brunswick
Issue date:	09/20/1978
From:	Hinckley D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20062B861	List: IR 05000324/1978020 ML20062B858
References
50-324-78-20, 50-325-78-20, NUDOCS 7811010402
Download: ML20062B869 (6)

Text

.

l

,

UNITED STATES

,(psb* E8 Coq'o,

,

NUCtEAR REGULATORY COMMISSION

g e R EGloN ll I ^ E lot MARIETTA STREET, * ATLANTA, GEORGI A 3o303

,f I s,.....

o,

.mj

~

Report Nos.: 50-325/78-20 and 50-324/78-20 Report Nos.: 50-325/78-20 and 50-324/78-20 Docket Nos.: 50-325 and 50-324 License Nos.: DPR-71 and DPR-62 License: Carolina Power and Light Company 336 Fayetteville Street Raleigh, North Carolina 27602 Facility Name: Brunswick 1 and 2 Inspection at: Southport, North Carolina Inspection conducted: August 15-18, 1978 Inspector: D. G. Hinckley Reviewed by: JC N-c " MA [7J H.' C. Dance, Chief Date Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch

,

Inspection Summary I

,

Inspection on August 15-18, 1978 (Report Nos. 50-325/78-20 and 50-324/78-20)

l Areas Inspected: Routine, unannounced inspection of records, licensee event reports, IE bulletins and circulars, and follow up on open item ,

('

The inspection involved 28 inspectors-hours onsite by one NRC inspecto Results: In the five areas inspected, no items of noncompliance or

,

deviations were identified.

1'

!

7812.01Cy o

.

.)

-

..

. .

RII Report Nos. 50-325/78-20 and 50-324/78-20 I-2 Records

.. The inspector reviewed the control of documents and records to verify that storage and retrieval requirements had been implemented as speci-fied in Administrative Instructions AI-2, Revision 9, " Collection, Maintenance, Control and Storage of Plant Records" and AE-6, Revision 9, " Plant Filing Instructions." The inspector verified that the following records were retrievable: APRM recording charts for 197 PT 3.1.7PC, Emergency Core Cooling System (Rev. 1), change review sign of shee System Description - SD-2 Automatic Blowdown System, master file cop RHR and EPCI room ventilation modification (MOD. 77-63) PT 45.2.6, Group I Valves Isolation Response Time, data sheets for 1977 tes Diesel generator trouble tickets for 197 Foreign Print VE&C Drawing No. 9527-0-25018, Revision 10, Reactor Coolant Recirculation System, Unit 1, Sheet Foreign Print VE&C Drawing No. 9527-LL-92037, Revision 6, MCC IXB, Comp. 1-DP7, Ventilation RER Heat Exchanger Area Fan IB, Cable Diagra The inspector discussed the as-built drawing filing system with the document control custodian but did not verify the control and distribu-tion of selected drawings. This verification will be done during a subsequent inspection. It was determined that a large backlog of needed revisions to existing drawings does exist. The as-built drawing l

revisions are necessary due to plant modifications. Many have been

'

completed for over six months, and the associated as-built drawings have not been revised. This problem was discussed with plant manage-ment; they indicated their awareness and concern.

i l .The inspector reviewed records of sixteen special test It was I

determined that safety evaluations were made as required by 10 CFR 50.5 The inspector discussed, with a licensee representative, the techniques used to monitor plant operations and equipment performance to permit

!

i I

I

. , ,

.

.

RII Report Nos. 50-325/78-20 and 50-324/78-20 I-3 detection of adverse trends or long-term equipment degradation. It was determined that instrument and equipment failures are being entered

..

into a computer file entitled, " Nuclear Plant Reliability Data System."

These data are to be used to help identify generic problem . Licensee Event Report Followup The below listed licensee event reports were reviewed in-office for potential generic problems, to detect trends, to determine if the information provided meets NRC reporting requirements and to consider whether corrective action discussed appeared appropriate. Selected reports, as denoted by asterisks, were further reviewed at the site to verify adequacy of information provided, corrective action taken and compliance with Technical Specifications and other regulatory require-ments. The inspector examined internal reports, correspondence, operating records and discussed events with appropriate personne LER N Date Event 1-78-52 6/7/78 Demineralized water storage tank low level

• 1-78-54 5/15/78 Torus sample line solenoid valve stuck closed

• 1-78-59 5/27/78 RCIC suction valve E51-F010 from CST stuck in closed position

• 1-78-60 5/26/78 Control rod 12-23 (positon 48) reed switch failure

• 1-78-61 6/7/78 Dry well to torus vacuum breaker CAC-X18G open position switch inoperable

• 1-78-62 6/14/78 Diesel generator building fire detection system inoperable

• 1-78-64 7/1/78 0xygen analyzer CAC-AQH-1259 inoperable

• 1-78-65 6/18/78 0xygen mouitor CAC-ATH-1263 out of calibration

• 1-78-66 7/2/78 Torus water temperature high

• 1-78-67 6/22/78 0xygen monitor CAC-AQH-1263 out of calibration

• 2-78-45 6/1/78 0xygen monitor CAC-AT-1263 power failure

• 2-78-46 5/is/78 " Full-in" reed switch for control rod 50-19 inoperable i

. .

.

.

.

RII Report Nos. 50-325/78-20 and 50-324/78-20 I-4 LER N Date Event

,

• 2-78-50 6/1/78 Drywell oxygen content high 2-78-51 6/2/78 HPCI turbine control response time abonormal

• 2-78-52 6/3/78 Personnel airlock door inoperable

• 2-78-53 6/2/78 Diesel engine driven fire pump tripped on over-speed

• 2-78-56 6/22/78 RBM channel "A" failure 2-78-57 6/27/78 RCIC turbine isolation signal on room cooler high differential temperture

• 2-78-58 6/30/78 Main steam line low pressure switch B21-PS-N015B out of calibration A supplemental response was requested for LER 2-78-5 This LER also addressed the inoperabilty of shutdown cooling isolation valve E11-F009, but did not discuss the reason for the valve being inoperable. No other problems were identifie . IE Circular and Bulletin Followup IEC 78-14, HPCI Turbine Reversing Chamber Hold Down Bolting. The inspection of the HPCI Turoine has been included in the 1979 outage list for both units. This circulatr is close IEB-78-06, Defective Cutler Hammer, Type M Relays. With DC Coil The licensee's investigation determined that relays of this type are not being used in safety-related systems or stocked in spare part This bulletin is close IEB 78-07, Protection Affored By Air-Line Resperators ans Supplied Air Hoods. The licensee stated that the respiratory protection program at ,

the BSEP does not use air supplied hoods or air-line supplied respira-tors operated in the demand made. This bulletin is close IEB 78-08, Radiation Levels from Fuel Element Transfer Tubes. The BSEP does not have a fuel transfer tube or high radiation areas adjacent to fuel storage. This bulletin is clos The above listed circular and bulletins were discussed with a licensee

. representative. The licensee's investigation correspondence and l

'

,

t

- .

. . .

.

.-

.

RII Report Nos. 50-325/78-20 and 50-324/78-20 *5

-

findings were reviewed. It was also determined that the licensee's responses to the bulletins were made in a timely manner. No problems

,

were identifie . Plant Tour The inspector made a tour of the Unit I and Unit 2 control room. A discussion was held with the control room operators concerning plant status. It was determined that the Unit 2 unidentified dry well leakage was in excess of 4 gpm (limit 5 gpm). The unit was scheduled for shutdown on August 19, 1978, to investigate

.

l l

,

~ , -