ML20062G371

Forwards IE Bulletin 78-14

ML20062G371
Person / Time
Site:	Callaway
Issue date:	12/19/1978
From:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Bryan J UNION ELECTRIC CO.
References
NUDOCS 7812280041
Download: ML20062G371 (1)

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UNITED STATES I

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NUCLEAR REGULATORY COMMISSION

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/ '9 / i n/,/ J/, e, Docket No. 50-483 I

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Docket No. 50-486 Union Electric Company ATIN:

Mr. John K. Bryan Vice President - Nuclear Post Office Box 149 St. Louis, MO 63166 Gentlemen:

The enclosed IE Bulletin No. 78-14 is forwarded to you for infor-mation. No written response is required. If you desire additional e

information regarding this matter, please contact this office.

Sincerely, C._.m h ga a d_-

famesGIKep%Ier Director

Enclosures:

1.

IE Bulletin No. 78-14 2.

List of IE Bulletins Issued in 1978 i

cc w/encls:

Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Regions I & IV Ms. K. Drey Hon. C. J. Frass, Chairman

, Missouri Public Service Commission DM (

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o U.S. NUCLEAR REGULATORY C0!t11SSION OFFICE OF INSPECTION A';D ENFORCEMD'I REGION III Dece=ber 19, 1978 IE Bulletin No. 75-14 DETERIORATION OF BL'NA-5 COMPONENTS IN ASCO SOLENOIDS Description of Circu stances:

Pellowing a reactor scra: at the Monticelle Nuclear Power Station on July 27, 1976, one control rod was deter =ined to have a slev scra:

insertion tice. While measuring the average control red scra: insertion tires (as required by Technical Specifications), the sa:e control rod failed to scra. Subsequent investigation revealed that a Buna-N disc in the scra: pilot valve selenoid core asse bly had fractured. 5:all pieces of the Buna-N caterial wedged between the core assembly and the valve pilot body. This prevented proper covement of the cere asse:bly (plunger), and thus prevented the valve fro: properly venting control air frc: the scra: valves. A sieflar event occurred during scra testing en June 5, 1976. On both occasions the control rod failed te scra during control rod surveillance testing. In these instances, had a scra: occurred during nor:a1 operation of the reactor, the affected rods would have inserted by action cf the backup scra solencid valves.

The reacter was placed in cold shutdow: on July 28, 1978. All cf the scran pilet selenoid valves and scra: backup valves were disasse bled and inspected. Six additional fractured Buna-N discs were found, all in scra: pilot selenoid valves. Northern States Power Company replaced the plunger Buna-N discs in all 242 scra: pilot valves and the 2 backup f

scra: valves.

i In addition to the Monticello failures, sieflar events were recently reported fro: the Big Rock Point and Pilgric facilities. At Big Rock Point, two failures were experienced in October while at Pilgri: one failure was found in July and two in Dece=ber. All t: these failures were encountered during surveillance testing.

General Electric had previously issued Service Informatien Letters, SIL 126 (March 31, 1975) and SIL 128 Revision 1 (January 30, 1976),

addressing the deterioration through natural aging of Buna-N co:penents in CRD scra pilot valves. These letters reconrended tha a caintenance progra: be adopted which replaced certain Buna-N components in scra:

pilot valves on a regularly scheduled basis. Hewever, the Buna-N discs g@

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IE Bulletin No. 78-14 December 19, 1978 in the scra pilot valve core assemblies were not included in these reconnendations. As a result of the Monticello experience and subsecuent investigation, General Electric has issued in August 1978. SIL 12E Revision 1, Supplement 1, which reconmends that all BWR operctors take the following actions:

" Establish a preventive caintenance progra to replace all core asse:blies, diaphrages and associated parts in all CRD scra:

pilot valves, backup scra: valves, scra: discharge volume vent and drain pilot valves, and scra: discharge volume test valves, at periodic intervals. The Buna-N parts used in these valves have at least a seven year shelf and in-service life fro: the packaging date on the rebuild kit. Thus, the valves should be rebuilt periodically te assure that the Buna-N parts are not used in excess cf seven years. It is reco== ended that the work be scheduled i=

any one outage such that the associated CR3s are selected fro: a distributed checkerboard pattern. The recaining valves can be rebuilt during subsequent outages."

For clarity, it is noted that the above seven year lirit recc== ended by CE includes all of the ti=c fro: packaging through installation to the end of service life. In addition, it is noted that the March 31, 1975 issue of SIL 128 stated that the design specification fer Buna-N specified a minicu: design life of three years.

Action to be Taken by Licensees:

For all GE BWE power reactor facilities with an operating license:

N-1.

Review Buna-N caterial applications in your control rod scra:

systems and detereine the time since installation, and for installed caterial, the time since packaging.

2.

Report the results of the review set forth in ite: 1 above and describe your schedule for replacement, both in response to this Bulletin and for periodic maintenance.

3.

Describe the bases for your schedule of replacement identified in response to ite: 2 above. Justify any proposed replacecent ti:e in excess of three years, lf i

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IE Bulletin No. 78-14 December 19, 1975 4.

Within 45 calendar days of the date of issue of this Bulletin, report in writing to the Director of the appropriate NRC Regional Office, the results of your review, schedule and bases for replacement with reEard to Ite=s 1 through 3.

A copy of your report should be sent to the L'nited States Nuclear ReEulatory Co==issien, Office of Inspection and Enforcement, Divisien of Reacter Operations Inspection, Washington, D.C.

20555.

For all BWR facilities with a construction perelt and all other power reactor facilities with an operating license or construction permit, this Bulletin is for information only and no written response is required.

Apprcved by CAO B180225 (R0072); clearance expires 7/31/80. Approval was given under a blanket clearance specifically for identified generic problems.

Enclosure:

l List of II Bulletins Issued in 1975 I

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IE Bulletin No. 78-14 December 19, 1978 LISTING OF IE BULLETINS ISSUED IN 1976 Bulletin Subject Date Issued Issued To Ne.

75-01 Fla==able Contact -

1/16/78 All Power Fencter Ar: Retainers in G.E.

Facilities with an CR120A Relays OL or CP 75-C2 Terrinal Block 1/30/78 All Power Reacter Qualification Facilities with an

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OL or CP 78-03 Potential Explosive 2/6/78 All Bk'E Power Gas Mixture Accu =ula-Reactor Facilities tiens Associated with with an OL or CP Bk'R Off as Syste:

E Operations 75-04 Environ ental Quali-2/21/78 All Power Reacter fication of Certain Facilities with an Ste: Mounted Lir.it OL or CP Switches Inside Reactor Containnent 75-05 Malfunctiening of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanit:-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reacter Eammer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle

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Tacilities with an CL, and all Priority 1 Material Licensees Page 1 of 2 9.

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l IE Bulletin No. 78-14 December 19, 1978 r

LISTINO OF IE BULLETINS ISSUED IN 1978 i

Bulletin Subj ect Date Issued Issued To No.

78-08 Radiatien Levels fro:

6/12/78 All Power and i

Tuel Element Transfer Research Reactor Tubes Tacilities with a Tuel Element transfer tube and t

'an OL.

C.

78-09 BWR Drywell Leakage 6/14/78 All BWR Power i

Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities l

Suppressor Accumulator with an OL or CP Spring Coils 78-11 Exa-ination of Mark I 7/21/78 B7E Power Reactor Containment Torus Tacilities fer Velds action:

Peach Botto: 2 and 3, Quad Cities 1 and l -

cello and Vermont

2. Hatch I, Monti-Yankee 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Tacilities with an Vessel Welds OL or CP 78-13 Failures in Source Heads 10/27/78 All General and i

of Kay-Ray, Inc., Gauges Specific Licensees Models 7050, 7050B, 7051 with Kay-Ray causes 7051B, 7060, 70603, 7061 and 7061B r

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