ML20062H108
| ML20062H108 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 04/18/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Howell S CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 7904270209 | |
| Download: ML20062H108 (1) | |
Text
o 7-oSa sto,(p, UNITED STATES j
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i PIE GION lil 799 ROOSEVELT ROAo g
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a oLeN aLLys. stusois som April 18, 1979 Docket No. 50-329 Docket No. 50-330 Consumers Power Company ATTN:
Mr. Stephen H. Howell Vice President 1945 West Parnall Road Jackson, MI 49201 Centlemen:
The enclosed IE Bulletin No.79-06A Revision No. 1, is forwarded to you
(
for information. No written response is required.
If yOJ desire addi-tional information regarding this matter, please contaer this office.
Sincerely, td.?nV
/
James G. Keppler i
Director
Enclosure:
IE Bulletin No.79-06A Revision No. I cc w/encle Central Files Director, NRR/DPM 7
Director, NRR/ DOR PDR s
Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Dr. Wayne E. North Myron M. Cherry, Chicago 7904g79,09
4 I
l U.S. NUCLEAR REGULATORY COMMISSION OTTICE OF INSPECTION AND ENFORCEMENT REGION III l
April 18, 1979 i
IE Bulletin No.79-06A (Revision No. 1)
REVIEW OT OPERATIONAL ERRORS AND SYSTEM MI$ ALIGNMENTS IDENTIFIED DURING TEE TERIE MILE IS!AND INCIDENT IE Bulletin 79-06A identified actions to be taken by the licensees of all pressurized water reactors designed by W atinghouse.
Item No. 3 of the actions to be taken, as stated in the original bulletin, was:
"3.
For your facilities that use pressurizer water level coincident with pressurizer pressure for automatic initia-tion of safety injection into the reactor coolant system, trip the low pressurizer level setpoint bistables such that, when the pressurizer pressure reaches the low setpoint, safety injection would be initiated regardless of the pres-l surizer level. In addition, instruct operators to manually i
initiate safety injection when the pressurizer pressure j
indication reaches the actuation setpoint whether or not I
the level itnlication has dropped to the actuation setpoint."
J.
i information from licensees and W atinghouse bas identified that implementation of this action would preclude the performance of surveil-i lance testing of the pressuriser pressure bistables without initiating
~
a safety injection.
j In order to permit surveillance testing of the pressurizer pressure bistables, the low pressuriser level bistables that must operate in coincidence with the low pressuriser pressure bistables any be restored to normal operation for the duration of the surveillance test of that 4
coincident pressuriser pressure channel. At the conclug4pn of the surveillance test of each pressuriser pressure channel, the coincident pressuriser level channel wat be returned to the tripped mode defined
'r ta Action Item 3 of IE Sulletin 79-06A.
As a result Itsa 3 should be revised as follows:
I l
7904250202 G
..y.,
IE Bulletin No.79-06A April 18, 1979 (Revision No. 1)
"3.
For your facilities that use pressurizer water level coincident with pressurizer pressure for automatic initia-tion of safety injection into the reactor coolant system, trip the low pressurizer level setpoint bistables such that, when the pressurizer pressure reaches the low setpoint.
safety injection would be initiated regardless of the pres-suriser level. The pressurizer level bistables may be returned to their normal operating positions during the pressurizer pressure channel functional surveillance tests.
In addition, instruct operators to manually initiate safety injection when the pressurizer pressure indication reaches the actuation setpoint whether or n. i the level indication has dropped to the actuation setpoint."
Item 13 of the actions to be taken, as stated in the original bulletin, was:
"13. Propose changes, as required, to those technical specifications which must be modified as a result of your implementing the above items."
Long term resolutions of some of these required actions may require design changes. Therefore, Item 13 of actions to be taken should be revised as follows:
"13. Propose changes, as required, to those technical specifications which must be modified as a result of your implementing the above items and identify design changes necessary in order to effect long term resolutions of these items."
For all light water reactor facilities designed by Westinghouse with an operating license, respond to Items 1-12 within 10 days of the receipt of this Bulletin. Respond to Item 13 (Technical Specification Change proposals and identification of design changes in 30 days.)
The other requirements of IE Bulletin 79-06A remain in effect.
Approved by GAO. B180225 (R0072); clearance expires 7-31-80. Approval l
was given under a blanket clearance specifically for identified generic problems.
Enclosure:
Listing of IE Bulletins Issued in Last 'Nelve Months l
l
s IE Bulletin No.79-06A (Revision No. 1)
April 18, 1979 LISTING OF IE Bt*LLETINS ISSUED IN LASI TVELVE MONDIS Bulletin Subject Date Issued Issued To Mc.
79-09 Failure of CE Type AK-2 4/17/79 All Power Reactor I
Circuit Breaker In Safety Facilities with an OL Related Systems 79-08 Rvents Relevant to BWR 4/14/79 A'1 BWR Power Reactor Reactors Identified During Facilities with an OL Three Mile Island Incident 79-07 Seismic Stress Analysis 4/14/79 All Power Reactor of Safety-Related Piping Facilities with an OL or CP 79-06B Review of Operational 4/14/79 All Combustion Engineer-Errors and System Mis-ing Designed Pressurized alignments Identified Water Power Reactor During the Three Mile Facilities with an Island incident Operating Licensee 79-06A Review of Operational 4/14/79 All Pressurized Water Errors and System Mis-Power Reactor Facilities alignments Identified of Westinghouse Design During the Three Mile with an OL Island incident 1
79-06 Review of Operational 4/11/79 All Pressurized Water Errors and System Mis-Power Reactors with an alignments Identified OL axcept R&W facilities During the three Mile Island Incident 79-05A Nuclear Incident at 4./5/79 All R&W Power Reactor Three Mile Island Pacilities with an OL 79-05 Nuclear Incident at 4/2/79
%'All Power Reactor Three Mile Island Facilities with an OL and CP Enclosure Page 1 of 3
i IE Bulletin No.79-06A (Revision No. 1)
April 18, 1979 LISTING OF IE BULLETINS ISSUED IN 1AST TWELVE MONDIS Bulletin Subject Date Issued Issued To No.
79-04 Incorrect Weights for 3/30/79 All Power Reactor Swing Check Valves Facilities with an knufactured by Velan OL or CP
{
Engineering Corporation 79-03 longitudinal Weld Defects 3/12/79 All Power Reactor in ASME EA-312 Type 304 Facilities with an Stainless Steel Pipe Spools OL or CP Manufactured by Youngstown Welding and Engineering Co.
79-02 Pipe Support Base Plate 3/2/79 All Power Reactor Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or CP 79-01 Environmental Qualifica-2/8/79 All Power Reaccor tion of Class IE Equipment Facilities with an OL or CP 78-14 Deterioration of BUNA-N 12/19/78 All CE BWR facilities Components in ASCO with an OL or CP 78-13 Pailures in Source Heads 10/27/78 All general and 4
of Kay-Ray, Inc., Gauges specific licensees Models 7950, 70505, 7051, with the subject 7051B, 7060, 7060B, 7061 Eay-Ray Inc.
and 70615 gauges78-12B Atypical Weld Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CF f
78-12A Atypical Weld Material 11/24/78
.. All Power Basetor in Reactor Pressure Facilities with an Tessel Welds OL. or CP 76-12 Atypical Wald h terial 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Walds OL or CP t
Enclosure Page 2 of 3 es
=
IE Bulletin No.79-06A (Revision No. 1)
April 18, 1979 LISTING OF IE BULLETINS ISSUED IN 1AST TWELVE MONTES Bulletin Subject Data Issued Issued To No.
78-11 Examination of Mark I 7/21/78 EWR Power Reactor Containment Torus Welds Facilities for action:
Peach Botton 2 and 3 Quad Cities 1 and 2 Batch I. Monticello and Vermont Yankee r
78-10 Bergen-Paterson Hydraulic 6/27/78 All BWR Power Reactor Shock Suppressor Accumulator Facilities with an Spring Coils OL or CP 78-09 BWR Dryvell Leakage Paths 6/14/79 All BWR Power Reactor Associated with Inadequate Facilities with an Drywell Closures OL or CP 78-08 Radiation Levels from Tuel 6/12/78 All Power and Research Element Transfer Tubes Reactor Facilities with a Fuel Element transfer tube and an OL 78-07 Protection afforded by 6/12/78 All Power Reactor Air-Line Respirators and Facilities with an OL, Supplied-Air Hoods all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees 78-06 Defective Cutler-Rammer 5/31/78 All Power Reactor Type M Relays with DC Colla Facilities with an OL or CP a.
Inclosure Page 3 of 3
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