ML17321A308
| ML17321A308 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/28/1984 |
| From: | Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| IEIN-84-16, NUDOCS 8412050168 | |
| Download: ML17321A308 (8) | |
Text
REGULATOR INFORMATION DISTRIBUTION TEM (BIDS)
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ACCESSION NBR: 8412050168 DOC, DATE-'4/1 1/28 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C-,
Cook Nucl ear Power Plant~
Unit 1i Indjana L
05000315 50 316 Donald C.
Cook Nuclear Power Plant~
Unit 2< Indiana L
05000316 AUTH INANE AUTHOR AF F ILIATION SMITHi l) ~ G ~
Indiana L Michigan Electric Co, RECIP,NAME RECIPIENT AFFILIATION Record Services Branch'Document Control Desk)
SUBJECT; Special.rept re-fire protection. sys,Grinnell Multi"Matic deluge. valves protecting Auxiliary Bldg 609 elevation"cask handling 8
587 elevation drumming room did not.satisfy surveillance. test Sys declared inoperable. in order to test.
DI'STRIBUTION CODE:
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OR Submittal:
Fir e Protection NOTES:
OL:10/25/70 OL: 12/23/72 05000315 05000316 RECIPIENT ID CODE/NAME'-
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Iec eoic INDIANA& MICHIGANEIECTRIC COMPANY DONALDC. COOK NUCLEAR PLANT P.O. Box 468, Bridgman, Michigan 49106 (616) 465-6901 f
November 28, 1984 Document Control Manager United States Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Operating License DPR-58/74 Docket Nos. 50-315/50-316 Document Control Manager:
This special report is being submitted to describe two similar events relating to fire protection systems at Donald C.
Cook Nuclear Plant.
The Grinnell Multi-Matic deluge valves protecting the Auxiliary Building 609'levation cask handling area and the 587'levation drumming room did not satisfy surveillance test procedure
- +120HP4030.STPe120 acceptance criteria which require the deluge valves to open upon actuation of their respective remote actuation valves.
The remote actuation valves bleed off detection line air, simulating the actuation of a single detection head in the pre-action air system.
Functional testing of deluge valves was initiated subsequent to an I.E.
inspection which took place during the summer of 1981.
The surveillance test procedure drafted to perform deluge valve testing was based upon manufacturer's literature which was felt at the time to provide adequate guidance.
Review of I.E. Information Notice 84-16 resulted in improve-ments to the test procedure to include actual opening of the deluge valve utilizing the actual preaction air line remote actuation valve.
The valves were tested in March of 1984 and satisfied the requirements of the then current version of **120HP4030.STP.120 (Rev. 7).
At approximately this same time research was initiated preparatory to the revision of STP.120.
This research resulted in the discovery that the preaction air supply and diaphragm chamber system lines to the actuator had been isolated, prior to the simulated actuation via the remote preaction air valve, in all previous revisions of the surveillance test.
Revision 8 of **120HP4030.STP.120 was first utilized on October 14, 1984 to test the cask handling area deluge system.
The procedural acceptance requirements were not satisfied and the system was declared inoperable.
Similar results were obtained on October 16 during the test of the drum-ming room system and it was also declared inoperable.
A detailed inves-tigation of the systems involved in the events resulted in the following:
8412050168 84ii28 PDR ADOCK 050003i5 8
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It was discovered that flow control orifices were not originally installed in the preaction air supply to the B-1 actuator.
Piston check valves were found installed in the preaction air supply line to the B-1 actuators, providing partial flow control.
The regulator for the preaction air supply had been set at approxi-mately 60 psi.
This setting should not have affected operability had the.050" inch flow control orifices been installed.
Corrosion products were found in the B-1 actuator.
Isolation of the preaction air supply line to the actuator in previous revisions of the surveillance test procedure had masked indications that the flow control orifices were not in place.
Flow control orifices and corrosion-resistant actuators are being obtained from the manufacturer.
The installed actuators have been cleaned and inspected and the preaction air supply regulator has been set at 30 psi.
The 30 psi setting allows adequate bleed-off of preaction air, upon simulated actuation, to cause the actuator to activate the deluge valve.
The systems have been tested and have met the surveillance test acceptance criteria.
Installation of the flow orifices will provide continued assurance of acceptable operation.
Though the two systems had been declared inoperable for failing to meet the acceptance criteria of the revised test procedure, the two systems would have actuated had the systems been challenged.
Indicated drops in detection line pressure during testing indicate that 2 3 preaction detection heads would have had to actuate to drop the preaction air supply pressure sufficiently to trip the respective deluge valve but the systems at all times retained the capability to perform their design function.
This report is being submitted pursuant to the requirements of Technical Specification 3.7.9.2 Action Statement (a) because the systems were de-clared inoperable in excess of 14 days to permit troubleshooting and test-ing.
The systems were returned to operable status on November 7, 1984 (cask handling area) and November 14, 1984 (drumming room).
Sincerely, M. G. Smith, Z'
Plant Manager
/mmf cc:
J.
E. Dolan J.
G. Keppler M. P. Alexich R. F. Kroeger D. Shermen, ANI H. Brugger R.
C. Callen, MPSC G. Charnoff, Esq.
J.
M. Hennigan E. L. Townley J.
F. Stietzel INPO PNSRC
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Novmeber 28, 1984 Distribution
{ Docket file wo/encl.
ORB//I Rdg wo/encl.
CParrish w/encl.
DWigginton w/encl.
DOCKET NO(S).
5P 315/316 Ifr. John Dolan, Vice Preskkd~
Xn&ana and.Michigan Electric Company c/o American Electric Power Service, Corporation 1 Mverside, Biheyetation
SUBJECT:
- Columbus, Ohio 43215 DeC COOK POWER PLANT UNITS IhHHD 2
-The following documents concerning our review" of the subject facility are transmitted for your information.
, 0 Notice of Receipt of Application, dated O Draft/Final Environmental Statment, dated D Notice of Availabilityof Draft/Final Environmental Statement, dated C3 Safety Evaluation Report, or Supplement No.
, dated H Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated C3'Monthly Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards
, Considerations, dated
'3 Application and Safety Analysis Report, Volume r
C3 Amendment No.
to Application/SAR dated C3 Construction Permit No. CPPR-
, Amendment No.
dated D Facility Operating License No.
, Amendment No.
D Order Extending Construction Completion Date, dated
, dated
& Other (Specify)
Mon hl Ho e co erin eriod Novmeber 21 1984 for hearia re uests and comments December 21 1984 iration date
. Division of Licensing Office of Nuclear Reactor Regulation
Enclosures:
As stated w/enclosure r Or< fCe~
ORBiI1:DL
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