IR 05000338/1978019

IE Inspec Rept 50-338/78-19 on 780717-20 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Included:Fire Prevention,Protec Prog,Lic Oper.Requal Training Prog,Plant Maint,Design Changes & Mods

ML20147C145
Person / Time
Site:	North Anna
Issue date:	09/01/1978
From:	Ashenden J, Bradford W, Skolds J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20147C137	List: IR 05000338/1978019 ML20147C133
References
50-338-78-19, NUDOCS 7810110290
Download: ML20147C145 (8)

Text

.____ - _____ - -_- ______ -

_

,

vq,o O u~,1Eo mt .

NUCLEAR REGULATORY COMMISSION E[** arcg

.

ym((g P EasoN l1

• g *

5 '.t

101 M AR1ETT A r.l H t.FT, ATt ANTA, cEoRGIA 30303 o, 4 s...../

Report No.: 50-338/78-19 Docket No.: 50-338 License No.: NPF-4 Licensee: Virginia Electric and Power Company P. O. Box 26666 Richmond, Virginia 23261 Facility Name: North Anna Nuclear Power Plant Inspection at: North Anna Plant, Mineral, Virginia Inspection conducted: July 17-20, 1978 Inspectors: W. H. Bradford J. L. Skolds J. Ashenden L

Accompanying Personnel: P. J. Kellogg Approved by: _

6 P. J. Kellogg, Chief G 'Date Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Surnary Inspection on July 17-20, 1978 (Report No. 50-338/78-19)

Areas Inspected: Routine, unannounced inspection of fire prevention /

protection program, including fire protection organization, fire hazard control, control of ignition sources, fire fighting plans, quality assurance for fire protection, and controls over the fire protection systems; licensed operator requal'1fication training program; formal training and retraining programs for nonlicensed plant personnel; plant maintenance; and design changes and modifications. The inspec-tion involved 72 inspector-hours by three NRC inspector Results: In the five areas inspected no deviation or items of noncompliance were identifie tilI$W

- _ - - - -

_ _ _ _ __ _ _ _ - _ _ _ _ _ _ _ - - - _

l <

.

.

.

RII Rpt. No. 50-338/78-19 I-1 DETAILS I Prepared by: 2d . MF 7I W. H. Bradford,[Aeactor Inspector Date Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: July 17-20, 1978 Reviewed by: 5 %[

P. J. Kellogg, Chiel 3 !/!7M Dat'e Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Persons Contacted Virginia Electric and Power Company (VEPCO)

• W. R. Cartwright, Superintendet t, Station Operations

• Matt Stokes, Plant Fire Marshall

• M. S. Kidd, NRC Renident Inspector

• L. O. Goodrich, Sup rvisor, Mechanical Mainter.ance l

• P. Kinsey, Electrical Supervisor, Maintenance

• L. Smith, Resident Quality Control Engineer

• J. R. Harper, Instrumentation Supervisor

• D. C. Woods, VEPCO Engineering Elvin Wilson, Training Coordinator Alan D. Miller, Training Coordinator Floyd White, Deputy Fire Nbrshall

• Denotes those present at exit intervie . License.e Action on Previous Inspection Findings (Closed) (Unresolved item 76-25/1) Fire Prevention and Protection Implementing Procedures Threugh discussion with licensee manegement and by review of administrative controls and implementing procedures, the inspector verified that work controls had been established in vital areas which involve possible ignition sourers, the use of a fire watch, QA audit and surveillance, and that work is controlled by operations personnel. The inspector had no further questions on this ite . Unresolved Items None identified during this inspectio . _ _ _ - - _ _ _ - _ _ - -

I .

,

.

.

RII Rpt. No. 50-338/78-19 I-2 Exit Interview A management interview was conducted at the conclusion of the inspection on July 20, 1978, with Mr. W. R. Cartwright and other licensee staff members (denoted in paragraph 1). All subjects presented in these details were discussed. The licensee acknowledged the inspection finding . Fire Protectior and Prevention The inspector reviewed the licensee's fire protection and prevention program to verify that controls had been esta-blished which include:

-

Work control procedures which include welding and burning contro Plant operations approval and control of work done under the work control procedur A requirement for a fire watch for welding and burning operatiens with capability of communication with the control roo '

-

A requirement for QA surveillance during maintenance and modification of fire stop penetrations seal Assurance that the cable penetration sealing material is controlled and that sealing material is not substituted which could be flammabl Plant emergency procedures had been established which include fire fighting procedures for specific vital areas and energency procedures which provide for orderly plant shutdown in cases of loss of normal and preferred alternate cooling.

l The inspector reviewed the results of the latest fire insurance inspection which was ccnducted on January 3, 4, 5, 197 The inspector reviewed the fire protection / prevention technical specification surveillance test requirements, the fire protection /

prevention administrative controls and implementing procedure The inspector toured various areas of the facility to observe operations in progress, to inspect the general state of cleanliness, housekeeping and fire protection / prevention systems and conditior The inspector noted that cleaning following construction was in progress in some areas. There were other areas which renuired cleaning of left over construction material and other items. A list was made of these areas by the licensee. The licensee reported at the exit interview that cleaning in these areas had starte _ _ _ _ _ _

,

i

.

RII Rpt. No. 50-33S/78-19 I-3 The inspector used one or more of the following acceptance

,

criteria for the above items:

s Technical Specifications Appendices A and B of 10 CFR 50 Regulatory Guide 1.120, " Fire Fighting (Rules for Nuclear Power Plants)

Regulatory Guide 1.39, " Housekeeping Requirements for Water-Cooled Nuclear Power Plants" Section 5.2.3 of ANSI N4 Section 6 of Appendix A to Regulatory Guide 1.33 Within the areas inspected no deviations or items of noncompliance were identifie . Licensed Operator Requalification Program The inspector reviewed documents and training records to verify that a requalification training program for NRC licensed reactor operators (R0s) and senior reactor operators (SR0s) had been established and was consistent with the requirements of the licensee's approved Operator Requalification Training Program,

'

Section 6.4 of the Technical Specifications and Appendix A to 10 CFR 55. The inspector reviewed individual training records for eight licensed operators.

, Within the areas inspected, no items of noncompliance or deviation were identifie . Retraining and Replacement Training for Non_ licensed Personnel The inspector reviewed training related documentation and procedures and interviewed eleven nonlicensed personnel to verify that the training described in Administrative Procedure 12.0, " General Employee Training", was being provided for nonlicensed personnel and met the requirements of Section 6.4 of the Technical Specifi-

'

cations, ANSI N18.1-1971, and Section 13.2 of the FSA Interviews with female employees also confirmed that information had been provided to them with regard to prenatal radiation exposure. Within the areas inspected, no discrepancies were identified.

l . .

. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

.

RII Rpt. No. 50-338/78-19 II-1 DETAILS II Prepared by: . i /D J. L. Skolds, Reactor Inspector Date Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: July 17-20, 1978 Reviewed by:I/ jfg (W /!78 P.'J.kellogg/ Chief / / D'a t e Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Persons Contact,ed Virginia Electric and Power Company (VEPCO)

J. A. Ahladas, Station M2 nager

• W. Cartwright, Superintendent, Station Operations

• R. Kinsey, Electrical Superviscr Maintenance

• L. Goodrich, Supervisor, Mechanical Maintenance ,

• D. Smith, Resident Quality Control Engineer

• Matt Stokes, Fire Mcrshall

• J. Harper, Instrumentation Supervisor

• D. C. Woods, VEPCO Engineering

• M. 4 Kidd, NRC Resident Inspector

• Denetes those present at exit intervie . Licensee Action on Previous Inspection Findings Not inspecte . Unresolved Items None identified during this inspectio . Exit Interview See Details I, paragraph . Maintenance The inspector conducted a review of the following procedures:

~~

'

, , , . . . _ _ _ . _ _ _ _ _ _ _ _ . _

- _ _ _ __ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _

,

.

RII Rpt. No. 50-338/78-19 II-2 10! DATE TITLE 4863 4-18-78 Containment Access Door Gasket 4870 5-6-78 MS 111B Leaking 4873 4-28-78 TI 1410 Cold Leg Wide Range Failed 4931 4-25-78 Rod Drive MG Set 1A Excessive Vibration 4975 5-23-78 Leakage from Check Valve 1-FW-47 5004 4-30-78 FI 1484 Reads Hi 5085 5-8-78 Low Voltage Power Supply NQ602 Ouc of Spec 5107 5-11-78 Repair Seat Leakage on MS-111A 5111 5-24-78 Change Out Pressurizer Pressure Transmitters 5142 5-24-78 RMS - 162 IndicatinggHigh 5183 5-16-78 Inner Seal On Containment Personnel Hatch Leaks 5305 5-21-78 Diesel Battery IJ 5316 5-25-78 Containment Instrument Air 5330 5-24-78 Start Problem with Pump Logic Relays 5337 5-24-78 Check 1-RC-P-1C For Oil Leak 5345 5-24-78 Replace Card TS442D 5352 5-27-78 1-NS-P-1B Appears to Have Blown Oil Seal 5355 5-26-78 Repack MOV-SI-1890C 5361 5-26-78 Replace B&D Incore Detectors 5369 5-27-78 MOV-1275A Packing Leak 5383 5-28-78 HCV-1557A is Mechanically Binding 5388 5-27-78 FCV 1113B Leaking 5392 5-27-78 Containment Inst Air Compressor 5393 5-27-78 RWST Level Indicator LT-QS-1000 Reading High

- _ _ _ _ _

l

.

.

RII Rpt. No. 50-338/78-19 II-3 MR DATE TITLE 5416 5-29-78 Pretection UT Cold Leg AMP on "A" Loop Failed 5440 5-31-78 Replace Rupture Discs on TV-MS-101 A, B, C 5526 6-6-78 1-QS-P-1A Breaker Will Not Close Remotely 5693 6-17-78 RMS-GW 101 Power Supply Reading High The maintenance was reviewed to verify that:

-

The limiting condition for operation was met while components or systems were removed from service for maintenanc The ms.intenance activities were accomplished using approved procedures by qualified personne The maintenance activities were functionally tested or calibrated as necessary priot to returning the components or system to servic The required administrative approvals were ob,tained

"

prior to initiating maintenance activitie The maintenance activities were inspected in accordance with the licensee's requirement The inspector used one or more of the following acceptance criteria for the above items:

-

Final Safety Analysis Report

-

ANSI 18.7-1972

- Technical Specifications

- Nuclear Power Station Quality Assurance Manual Findings were acceptabl . Design Changes and Modifications The inspector conducted a review of the following design changes and modifications:

_ _ _ _ _ _ _ _ - _

. . .. :

. . . . ,

. 1 RII Rpt. No. 50-338/78-19 II-4 l Design Change N Title 77-01 Install Feed Flow Transmitters '

78-01 Recire Spray /LHSI Cross Connect 78-05- Casing Cooling Tie-In i 78-09 Boric Acid Transfer Pump Insulation 78-27 Pressurizer Pressure Transmitter 78-38- MSIV Modification The design changes were reviewed to verify that:

-

The design changes were made in accordance with 10 CFR 50.59,

-

The design changes were reviewed and approved in accordance with Technical Specification l

-

The design changes were performed in accordance with formal procedure Acceptance tests were performed following design changes to ,

'

ensure operability and confonaance to Technical Specification w The inspector used one or more of the following acceptance criteria for the above items:

- Final Safety Analysis Report

-

10 CFR 50.59

-

ANSI 18.7-1972

-

ANSI 45.2.11-1974

-

Nuclear Power Station Quality Assurance Manual Findings were acceptabl i i

e I

('

>

4 . _ __ _ _ _ .