ML19344E880
| ML19344E880 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 08/22/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Crane R PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8009120029 | |
| Download: ML19344E880 (1) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
,E REGION V o
1990 N. CALIFORNIA BOULEVARD g * *,, *,&g SUITE 202. WALNUT CREEK PLAZA WALNUT CREEK, CALIFOHNIA 94506 August 22, 1980 Docket No. 50-133 Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106 Attention: Mr. Philip A. Crane, Jr.
Assistant General Counsel Gentlemen:
Enclosed is IE Supplement No. 3 to Bulletin No. 80-17 which requires action by you with regard to your power reactor facility (ies) with an operating license.
In order to assist the NRC in evaluating the value/ impact of each Bulletin on licensees, it wo>ld be helpful if you would provide an estimate of the manpower expended in conouct of the review and preparation of the report (s) required by the Bulletin.
Please estimate separately the manpower associated with correc-tive actions necessary following identification of problems through the Bulletin.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, i
ACb R. H. Engelken l
Director
Enclosures:
1.
IE Supplement No. 3 to Bulletin No. 80-17 2.
Recently. issued IE Bulletins cc w/ enclosures:
J. D. Shiffer W. A. Raymond, PG&E E. Weeks, PG&E, Humboldt Bay
.8009120.N 9
SSINS: 6820 Accession No.:
8006190074 UNITED STATES MUCLEAR REGULATORY CCMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 22, 1980 IE Supplement 3 to Bulletin No. 80-17:
FAILURE OF CONTROL RODS TO INSERT DURING A SCRAM AT A BWR NRC staff evaluation of a potential single failure techanism of the control rod drive control air system has identified the need for licensee actions in addition to those recuested by IEB 80-17 and Supplements 1 and 2.
The potential single failure was discussed in IE Information Notice 80-30, which was issued on August 19, 1980.
It involves gradual or partiel loss of control air system pressure, which could cause partial opening of scram outlet valves without rod motion.
The resultant accumulated seal leakage could conceivably fill the scram discharge volume in a few minutes. Since not all operating BWR's have instrumentation presently installed to continuously indicate water level in the scram discharge volume needers and to provide a control room alarm or scram function, the possibility exists for the scram discharge volume to fill to a level which could prevent reactor scram before automatic protective action or before the operators could be warned.
In view of the possible single failure techanism described above, the following actions are requested in addition to those specified in IE Bulletin 80-17, Supplements 1 and 2:
1.
For those plants in which the scram discharge volute headers are connected to the instrument volume by a 2 inch pipe, within five days of the date of this Bulletin, provide or verify that procedures are in effect to:
a.
Require an imrediate manual scras or low control rod drive air pressure with a mininum 10 psi margin above t.r opening pressure of the scram outlet valves.
b.
Require an incediate manual scram in the event of:
(1) !!ultiple rod drift-in alarms, or (2) A marked change in the number of control rods with high temperature alarms.
Installation of water level instrumentation in the scram discharge volume
.with level alarn and continuous level indication in the control room, in response to Item B.1 of IEB 80-17 Supplement No.1, may provide a basis for relaxation of the tice for initiating a manual scram.
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IE Bulletin No. 80-17 August 22, 1980 Supplement No. 3 Page 2 of 2 2.
In addition, every BhR licensee is requested within five days of the date of this bulletin to provide and implement procedures which require a functional test using water for the instrument volume level alarm, rod block and scram switches after each scram event, before returning to power. This procedure should remain in effect until modifications in addition to Item B.1 of IEB 80-17 supplement No.1 are completed to substantially increase reliability of water level indication in the scram discharge volume (s).
Licensees of all operating BWRs shall submit a report summarizing action taken in response to the above items within 10 days of the date of this Bulletin Supplement.
Accordingly, you are requested to provide within 10 days as specified above, written statements of the above information signed under oath or affirmation.
Reports shall be submitted to the Director of the appropriate NRC Regional Office and a copy forwarded to the Director, Division of Reactor Operations Inspection, NRC. Office of Inspection and Enforcement, Washington, D.C.
20555 Approved by GAO, B180225 (R0072); clearance expires July 31,1980. (Application for renewal pending before GA0.) Approval was given under a blanket clearance specifically for identified generic problems.
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IE Bulletin fio. 80-17 August 22, 1980 Supplement 3 RECENTLY ISSUED IE BULLETINS Bulletin fio.
Sub,iect Date Issued Issued To 80-20 Failures of Westinghouse 7/31/80 To each nuclear Type W-2 Spring Return power facility in to fleutral Control Switches your region having an OL or a CP 80-19 Failures of Mercury-7/31/80 All nuclear power Wetted Matrix Relays in facilities having Reactor Protective Systems either an OL or a CP of Operating Nuclear Power Plants Designed by Combus-tion Engineering 80-18 Maintenance of Adequate 7/24/80 All PWR power reactor Minimum Flow Thru Centrifugal facilities holding OLs Charging Pumps Following and to those PWRs Secondary Side High Energy nearing licensing Line Rupture Supplement 2 Failures Revealed by 7/22/80 All BWR power reactor to 80-17 Testing Subsequent to facilities holding OLs Failure of Control Rods to Insert Dering a Scram at a BWR Supplement 1 Failure of Control Rods 7/18/80 All BWR power reactor to 80-17 to Insert During a Scram facilities holding OLs at a BWR l
80-17 Failure of Control Rods 7/3/80 All BWR power reactor to Insert During a Scram facilities holding OLs i
at a BWR 80-16 Potential liisapplication of 6/27/80 All Power Reactor l
Rosemount Inc., Models 1151 Facilities with.an l
and 1152 Pressure Transmitters OL or a CP l
with Either "A" or "D" Output Codes 80-15 Possible Loss Of Hotline 6/18/80 All nuclear facilities With Loss Of Off-Site Power holding OLs l
80-14 Degradation of Scram 6/12/80 All BWR's with an l
Discharge Volume Capability-OL
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