IR 05000133/1979001
| ML19224D212 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 05/03/1979 |
| From: | Morrill P, Sternberg D, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19224D205 | List: |
| References | |
| 50-133-79-01, 50-133-79-1, NUDOCS 7907110092 | |
| Download: ML19224D212 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE of INSPECTION AND ENFORCEMENT REGIoS V 50-133/79-C1 Report No.
DPR-7 safeguards croup
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50-133 ticense no, Docket No.
Licensee:
Pacific Gas and Flectric Company
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77 Beale Street San Francisco, California 94106 Facility Name:
Humboldt Bay Unit 3 Inspection at:
Eureka, California Inspection conduc,ted:
flarch 20-23, 1979
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Inspectors:
J%
P.
. Morrill, Re' actor Inspector Date signed
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Date Signed Date Signed
Approved By J
bw L9 h
b D. Sternberg, Chief, Rehctdr Project Section 1,
/ nite st' anes Reactor Operations and fluclear Support Branch S urrra ry :
Inspection on March 20-23,1979 (Report f;o. 50-133/79-01)
Areas Inspected:
Routine, unannounced inspection of operations; change; to procedures; fire protection / prevention; followup on IE Bulletins and Circulars; followup on Licensee Event Reports and independent inspection.
The inspection involved 21 insoector-hours onsite by one NRC inspector.
Results:
fio items of noncompliance or deviations were identified.
RV Form 719 (7)
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, u 790711007M
. F DETAILS 1.
Persons Contacted
- E. Weeks, Plant Superintendont
- U. Rapp, Senior Power Production Engineer S. Redeker, Power Production Engineer R. Twiddy, Quality Control Engineer
- M. Barham, Quality Assurance Analyist R. Chaffe, Plant Fire Marshall The inspector also interviewed other licensee employees during the course of the inspection including control operators, shift forenen, maintenance personnel, and office personnel.
- Denotes those present at the exit interview on March 23, 1979.
2.
Orcanization f1r. E. Week 3 has been promnted to the position of Plant Superintendent.
Mr. W. Raymond has been pr ated to the position of Quality Assurance Director at the corporate offices ir, aan Francisco.
3.
Plant Operatiens The major items remaining to be completed during the outage have been deferred until resolution of the geolog:c/ seismic issues at the plant, fio major work was observed to be in progress during this inspection.
The inspector walked through areas of the plant to observe activities in progress, to inspect the general state of housekeeping, and to check that monitoring instrumentation was reading or recording as required.
Temperature and nuclear monitoring indications appeared normal.
The inspector observed that neutron nonitoring was being performed in accord-ance with Technical Specification requirements.
flormal radiation control practices were in effect including the establishment of barrier controls.
fio unusual fluid leaks or piping vibrations were observed.
The ventilation systems, nuclear instrumentation, component cooling system, and reactor protection systems were in operation during this tour.
Representative samples of the following logs and records from f!ovember 9, 1978 to February 9,1979, were examined and discussed with licensee personnel:
Control Operator's Log Shif t Foremen's Log Jumper Log Clearange 1. cgs Plant Staf f Review Comittee Minutes tio items of noncompliance or deviations were identified.
1-J O' 1 q?f Let
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Procedures The inspector examined the current procedures listed below to verify that changes to these procedures, as well as new procedures, are in conformance with regulatory requirements and that the technical adecuacy of reviewed procedures is consistent with the intended rode of operation.
The inspector also examined 3 elected Planc Staff Review Committee minutes to verify that technical specification requirement; were met.
Adninistrative Procedures B-51, Dissemination of Training Information to Plant Personnel B-52, Cualification and Training Requirements of Personnel Specifically Concerned with Fire loss Prevention B-650, Security Force Training Progran C-1, Supplerent ho.1, Design Changes C-3, Supplenent No.1, Surveillance Testing Progran C-12, Supplenents 1 and 2, Resolution and Reporting of Plant Probl ais C-151, Change of Plant Operational Condition or Equipment Status D-4, Supplement No.1, Local Order of Safety Related Material and Sert ices D-55, Equipment Restricted fron Nuclear Safety Application at Humboldt Cay Power P1 ant Eauipment Descrittion and Operating Instructions A-2, Standard Instructions for Clearances B-1, Reactor B-2, Control Rod Drive Systen B-5, Reactor Clean-up Systen B-6, Reactor Shutdown Cooling System B-7, Engineered Safeguards Systems B-7a, Safeguards System Valving B-7b, Core Spray B-10, Spent i al Storage Pit Energy Absorber B-18, Drywell and Suppression Chanber Inverting D-9, Closed Cooling Water System H-6, Annunciator System Emergency Operatino Procedures E0P-1A, Pipe Break Inside Drywell E0P-1B, Pipe Break in Pipe Tunnel E0P-7A, Loss of Emergency Condenser Following Initiation E0P-8E, Loss of Closed Cooling Water ECP-9A, Loss of Feedwater
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-3-Ooerational Test Procedures
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OTP-12, Reactor Safety System Routine Check During Operation OTP-23, Functional Test of the Core Spray Pumps No items of noncompliance or deviations were identified.
5.
Fire Prevention and Protection The inspector examined licensee procedures and records, discussed fire protection training and drills, and toured the facility with th' Fire Brioade Chi.ef to verify inglenentation of the fire orotection chnical specifications.
The following items were examined and discussa. with licensee personnel.
Procedures Administrative Procedures A-51, Fire Loss Prevention B-2, Supplement tio. 3, Fire Brigade Training Program C-13, Supplerent No. 2, Control of Ignition Sources Equiptrent Description and Operating Instructions A-5, Operability Requirements J-6, Fire Protection Emergency Operating Procedure E0P-20, Plant Fire and/or Explosion Potentially Affecting Unit l'o. 3 Operational Test Procedure OTP-14, Fire Hose Testing Reports PG&E, Safety Health and Claims Department Fire Protection Inspection - January 15, 1979 Nuclear itaterial Limited Fire Protection Inspections -
January 15, 1979 and April 27, 1978 Manuals Fire Brigade Training Manual 33}.
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-4-Records Fire Drill Critiques Plant Safety Raview Comittee flinutes Surveillance records For:
Fire Pump Tests Sprinkler Tests Fuel Oil Analysis for Fire Pump Testable Valve Cycling
/4nnual Fire Fose and !tozzle Test and Inspections Training Pecords (attend.ince sheets)
fio items of noncompliance or deviations were identified.
6.
Reportable Event Follo up_
The circunstances and corrective action described in the Licensee Event Report listed below was verified by the inspector through an examination of selected records, interviews with responsible personnel, and examinat on of equipment. The event had bcen reviewed by the licensee and reportint, requirements were met.
The event prcmpted a design change to the fire pump pining.
The design change package and 10 CFR 50.59 review were exanined.
The corrective actions identified in the LER are completed.
LER 78-003/03L-l'.
Failure of the relief valve to the number 3 fire /LPCF pump due to improper installation of the relief valve.
(Closed)
flo items of noncorpliance or deviations were identified.
7.
Followup on IE Nrculars and Bulletins _
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The inspector verified that the plant staff had received the IE Circulars and Bulletins listed below. An examination of records and discussions with licensee representatives verified that appropriate correctiva action was identified or taken as follows:
Circul ars 76-07, Inadequate Perfornance by Reactor Operating and Support Staff foembers:
The licensee's procedures for Hunboldt Bay Unit f;o. 3 have been revised to reflect the problems identified.
(Closed)
78-02, Proper Lubricating Oil for Terry Turbines:
There are r.a Terry Turbines at the licensee's Hutboldt Facility.
The licensee is reviewing the circular's information as applicable to nonsafety related turbines.
(Closed)
331 030
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-5-78-06, Potential Ccwon flode Flooding of ECCS Equipnent Rocas at E'JR Facili ties.
This item is being review ' by cognizant licensee personnel.
Licensee representatives ated that appro-priate corrective measures would be taken prior to resumption of operation.
(0 pen)
78-15, Tilting DISC Check Valves Fail to Close with Gravity in Vertical Position:
Licensee perscnnel completed a review of plant check valves which verified that check valves were properly installed.
(Closed)
78-16, Lintorque Valve Operators: Licensee representatives stated that this was being reviewed and that appropriate corrective measures would be taken prior to resumption of operations.
(0 pen)
Bulletins Bulletin flos. 76-01, 76-04, 78-03 and 78-09 remain open.
Licensee Representatives stated that these open items are under review and appropriate corrective measures will be taken prior to resumption of plant cperations.
flo items of noncompliance or deviations were identified.
8.
Independent Inspection The inspector examined the licensee's augrented off-gas treatment system to verify adequate instrumentation and alarms were available to provide indication of abnormal conditions to the plant operators.
The inspector also verified that the licensee had eliminated potential hydrogen release paths and had identified methods of detecting potentially explosive hydrogen /
air mixtures in the appropriate locations.
flo items of noncompliance or deviations were identified.
9.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on flarch 23, 1979.
The purpose and scope of the inspection was summarized by the inspector. The licensee was advised that no itens of noncompliance or deviations were identified.
331 OH