ML17321A350
| ML17321A350 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/10/1984 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:07750, AEP:NRC:7750, NUDOCS 8412140230 | |
| Download: ML17321A350 (11) | |
Text
REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION'BR; 80121402/0 DOC ~ DATE, SLY/12/10 NOTARIZED:
NO FACIL:50 315 Donald C'
Cook Nuclear Power Plantg Unit l~ Indiana L
50"316 Donald CD Cook Nuclear Power Plants Unit 2~ Indiana AUTH BYNAME AUTHOR AFFILIATIO~
ALEXICH<M~ P ~
Indiana L Michigan Elect ic Co ~
RECIP ~ NAME RECIPIENT AFFILIATION DENTONeH ~ RE Office of Nuclear Reactor RegUlationi Director
SUBJECT:
Forwards revised justife'ications for continued operation re electrical equipmegt environ qualification program,Rev corrects -schedule for proposed corrective actions 8
accurately describes operability of hot 8 cold leg temps+
DISTRIBUTION CODE:
A008D COPIES RECEIVED:LTR'NCL 'IZE".
TITLE', OR/L'icensing Submittal:
Equipment Qualification NOTES!
OL:
10/25/7'L:
1? /23/72 DOCKET 05000315 05000316 0500031'5 05000316 RECIPIENT ID CODE/NAME.
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 December 10, 1984 AEP:NRC:07750 Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
DPR-58 and DPR-74 ELECTRICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION (10 CFR 50.49);
UPDATE TO LETTER NO. AEP:NRC:0775N Mr. Harold R. Denton, Director Office of Nuclear Reaotor Regulat1on U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
By letter dated October 18, 1984
[AEP:NRC:0775N, Mr. M. P. Alexich, Ind1ana 5 Michigan Electric Company (IMECo), to Mr. H. R. Denton,
- NRC3, IMECo responded to an NRC staff request'nd provided addit1onal information with regard to the Donald C. Cook Nuclear Plant electrical equipment environmental qualification program.
This information was intended to form the basis for your staff's final review of the Cook Plant 10 CFR 50.49 environmental qualification program, allowing for the issuance of a Safety Evaluation Report on this topic.
As noted in IMECo letter No. AEP:NRC:0775N, the Plant Nuclear Safety Review Committee and the Nuclear Safety Design Review Committee had not yet reviewed the technical Justificat1ons for Continued Operat1on (JCOs) at the time of transmittal.
These reviews have now been completed, and as a result revisions have been prepared for two of the JCOs previously submitted.
The two revised JCOs are provided in the attachment to this letter, and update JCO Nos.
6 and 8 contained in Attachment 2 to AEP:NRC:0775N.
In the oase of JCO No. 6, the revision corrects the schedule for proposed oorrective actions to agree with the AEP:NRC:0775N cover letter.
For JCO No. 8, the revision more accurately descr ibes the operability of the hot and cold leg Reaotor Coolant System resistance=-temperature detectors
- and, as back-up indication, the use of the main steam pressure transmitters 1n con)unction with saturated steam tables.
The two attached JCOs supersede the two JCOs whioh were previously submitted for these equipment items.
8412i40230 841210 PDR ADOCK 05000315 P
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Mr. Harold R. Denton AEP NRC 07750 This document has been prepared following Corporate procedures whioh incorporate a reasonable set of controls to ensure its accur acy and completeness prior to signature by the undersigned.
Very truly yours, MPA/dam Attachment M. P.
A exAeh Vice President
~9.
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John E. Dolan N.
G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector Bridgman
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Donald C. Cook Nuclear Plant No(s).:
Equipment Manufacturer:
"<< APPlicable Equipment Model/item No(s).:
Not APPlicable Equipment
Description:
Cable Termination at Reactor Coolant System Vents Solenoid-Operated Valve System Component Evaluation Worksheet No(s).:
Plant gdentification No(s).:
ot APPlicable
~
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Outstanding Equipment Qualification Deficiencies:
Justification For Continued Operation (check one or more of the following, and explain on the next page):
(a)
The safety function may be accomplished by some designated alternative equipment if the principal equipment has not been demonstrated to be fully qualified.
(b)
The validity of partial type test data in support of the original qualification has been considered.
(c)
(d)
Z (6)
There is limited use of administrative controls over equipment that has not been demonstrated to be fully qualified.
-The safety function.,villbe,completed prior,to exposure to the
. accident environment r'esulting from the design basis "event,'nd.
subsequent failure of the equipment will not degrade any safety function or mislead the operator.
Failure of the equipment under the accident environment resulting from the. design basis event will not lead to significant degradation of any safety funotion or misleading information to the operator.
U E
0 Explanation of Justification For Continued Operation Noted on Previous Page:
The Reactor Coolant System vents are a post-TMI lessons learned require-ment.
E ui ment installation without roof of ualification was NRC-mandated.
When the environmental qualification test configuration details became availa-ble during the sprin of 1984, we realized that our installation did not con-form with the qualified installation.
In their qualification test, Westinghouse used a Conax connector to pre-elude the possibility of steam and chemical spray from entering the solenoid enclosure and reacting with the electrical terminations.
Since we had not been made aware of the details of the test configuration, the solenoid valves were installed with a metal conduit with no protection against a steam envir-onment.
In order to change the installed ele'ctrical connections to agree with those used by Westinghouse in their qualification test, a plant design change is in process.
The electrical connection should be modified during the 1985 refueling outages for each unit of the D. C.
Cook Nuclear Plant (i.e., those outages anticipated to begin in March 1985 for Unit 1, and in November 1985 for Unit
- 2).
Donald C. Cook Nuclear plant No(s).:
Units 1>>d 2
Equipment Manufacturer S. Moore, Boston Insulated Wire, Cerro Wire a Cable Equipment Model/Ztem No(s).:
Equipment
Description:
cables for Resistance Tem erature Detectors RTDs In Reactor Coolant S stem Hot and Cold Le s system component Evaluation worksheet No(s).:
cI-3 cI-5 Unit 1
. cI-8 CI-9, CI-11 (Unit 2)
Plant Identification No(s).:
Not A licable
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Outstanding Equipment Qualification Deficiencies:
Submer ence Justification For Continued Operation (check one or more of the following, and explain on the next page):
x (g)
The safety function may be accomplished by some designated alternative equipment if the principal equipment has not been demonstrated to be fully qualified.
(b)
The validity of partial type test data in support of the original qualification has been considered.
(c)
There is limited use of administrative controls over equipment that has not been demonstrated to be fully qualified.
The safety'unction will be'ompleted prior to expoaur e to the, accident environment result'ing from the design basis event, and subsequent failure of the equipment will not degrade any safety function or mislead the operator.
(e)
Failure of the equipment under the accident environment resulting from the design basis event will not lead to significant degradation of any safety function or misleading information to the operator.
U E
Explanation of Justification For Continued Operation Noted on Previous Page:
NTR-110, -120, -130, -140, -210, -220, -230, and -240 are Resistance Temperature Detectors (RTDs) located in the hot and cold le i in of the four reactor coolant loops.
The cables for six of the ei ht NTRs were inad-vertently routed below the maximum containment flood level elevation in each unit.
The remaining two NTR cables (coolant loop Nos.
1 and 3 hot le
) in each unit were,
- however, routed above the maximum flood level lane.
Hot leg temperature information is therefore available for'oolant loo Nos.
1 and 3 in both units of the D. C. Cook Nuclear Plant.
Additionall the average coolant loop temperature, T
, can be obtained by usin the main steam pressure transmitters outside containment in conjunction with saturated steam tables.
The cold leg temperature for coolant loop Nos.
1 and 3 may then be computed from T and T for these loops.
The six NTR cables routed below the maximum containment. flood level plane in each unit will be rerouted.
A design change has been issued to cover this work, and is expected to be completed during the 1985 refueling'outages for each unit of the D. C. Cook Nuclear Plant (i.e., those outages anticipated to
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begin in March 1985 for Unit 1 and in November 1985 for Unit 2).
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