ML17331A281
| ML17331A281 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/16/1993 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0692CK, AEP:NRC:692CK, GL-92-08, GL-92-8, IEB-92-001, IEB-92-1, NUDOCS 9304210291 | |
| Download: ML17331A281 (12) | |
Text
ACCELERATPD DOCUMEN"I DIST BUTION SYSTEM REGULAT INFORMATION DISTRIBUTION YSTEM (RIDS)
'0 ACCESSION NBR:9304210291 DOC.DATE: 93/04/16 NOTARIZED: YES DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
I
SUBJECT:
Forwards response to GL 92-08, "Thermo-Lag 330-1 Fire Barriers." Facilities do not utilize subj barriers to protect cables
& conduits necessary for safe shutdown from fire damage. Fire watches posted per NRC Bulletin 92-001.
DISTRIBUTION CODE:
A029D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Generic Letter 92-008 Thermal-Log 330 Fire Barrier NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA DEANgW INTERNAL: NRR/DET/EELB NRR/PD3-1 RGN3
....FILE EXTERNAL: NRC PDR COPIES LTTR ENCL 1
0 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME.
PD3-1 PD NR JX~S LB WEG~ILE Ol NSIC COPIES LTTR ENCL 1
1 2
2 1
1 1
1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
D TOTAL NUMBER OF COPIES REQUIRED:
LTTR 11 ENCL 10
Indiana Michigan Power Company P.O. Box 16631 CoIumbus, OH 43216 Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
RESPONSE
TO NRC GENERIC LETTER 92-08i "THERMO-LAG 330-1 FIRE BARRIERS" AEP;NRC:0692CK U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 Attn: T. E. Murley April 16, 1993 Dear Dr. Murleyr This letter provides our response to NRC Generic Letter 92-08.
The specific information requested by the generic letter is provided in the attachments to this letter.
As the generic letter allows, our response refers to our previous responses to Bulletin 92-01 and Supplement 1 to Bulletin 92-01.
In
- summary, Cook Nuclear Plant does utilize Thermo-Lag 330 to protect cables and conduits that are necessary for safe shutdown from fire damage.
As a result of Bulletin 92-01, fire watches were posted in the areas of Cook Nuclear Plant where Thermo-Lag 330 material was utilized as a 1-or 3-hour barrier to protect safe shutdown equipment, including all sizes of
- conduits, wallsg
- ceilings, and equipment enclosures.
With respect to long-term corrective actions, we will consider application of the results of NUMARC's efforts when completed.
Our response to NRC Generic Letter 92-08 was requested to be made under oath or affirmation according to the provisions of Section 182a of the Atomic Energy Act of 1954, as
- amended, and 10 CFR 50.54(f).
As such, an oath is included with this letter.
Sincerely, E'E'ice President dgr Attachments ccr A. A. Blind-Bridgman J.
R. Padgett G. Charnoff NFEM Section Chief A. B. Davis >> Region III NRC Resident Inspector Bridgman
.XBAv.a.r 9aOOa10~91 Saoe1S PDR ADOCK 05000315 P
'DR
1 t
STATE OF OHIO)
COUNTY OF FfVLMCLIN)
E. E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing response to NRC GENERIC LETTER 92-08 and knows the contents
- thereof, and that said contents are true to the best of his knowledge and belief.
Subscribed and sworn to me before this day of 19 NOTARY PUBLIC RITA D. HILL ffOTAPY PUN.IC. STATE OF OHIO
j
/~
/p
<re I"
ATTACHMENT 1 TO AEP:NRC:0692CK REPLY TO NRC GENERIC LETTER 92-08
Attachment 1 to AEP:NRC:0692CK Page 1
The numbered responses provided below correspond to the associated numbered reporting requirement in the generic letter.
The previous responses, AEPtNRCtll76 dated July 24, 1992 and AEP:NRC:1177 dated October 5g 1992@ to NRC Bulletin 92-01 and Supplement 1 identified the uses of Thermo-Lag 330-1 at Cook Nuclear Plant.
These responses identified where this material was installed in the plant and that these installations were a licensing commitment intended to implement the requirements of 10 CFR 50 Appendix R.
2.(a)
Selection of Thermo-Lacy fire barriers was based upon acceptance criteria provided during the l984 workshops by the NRC at the time of initial installation and upon qualification test reports and other literature received from Thermal Science Incorporated (TSI).
Subsequent to the initial selection of the Thermo-Lag fire barriers, questions have recently arisen relative to the performance of the material and the conduct of previous tests that were used in the selection process.
The NRC has now specifically declared a large number of the previous tests, and their corresponding installationsg to be indeterminate.
This has resulted in the need to
- retest, re-evaluate and potentially upgrade the barriers.
The NUNARC Thermo-Lag test program is intended to provide generic testing and information necessary to identify corrective actions.
The results of this program will be used in the determination of specific corrective actions to be taken for Cook Nuclear Plant Thermo-Lag installations.
2e (b)
In general, the fire barrier configurations installed in the Cook Nuclear Plant represent the materials, workmanship, methods of
- assembly, dimensions, and configurations described in TSI technical notes addressing installation procedures and in test reports provided by TSI.
The installed configurations for Cook Nuclear Plant were performed in accordance with guidance made available by the NRC at a series of Regional NRC workshops held in 1984.
This guidance was ultimately included in NRC Generic Letter 86-10.
GL 86-10 states that where exact replication of a tested configuration cannot be achieved, the field installation should meet all of the following criteria:
2 ~
The continuity of the fire barrier material is maintained.
The thickness of the barrier is maintained.
3 ~
The nature of the support assembly is unchanged from the tested configuration.
The application or "end use" of the fire barrier is unchanged from the tested configuration.
For
- example, the use of a
cable tray barrier to protect cable tray which differs in configuration from those that were tested would be acceptable.
Attachment 1 to AEP:NRC:0692CR Page 2
- However, the use of structural steel fire proofing to protect,a cable tray assembly may not be acceptable.
~
The configuration has been reviewed by a
qualified fire protection engineer and found to provide an equivalent level of protection.
Deviations from TSI installation procedures were evaluated and documented by design engineers and/or fire protection engineers as appropriate.
- 2. (c)
The additional reduction of ampacity on cables was considered as part of the design change that installed the Thermo-Lag 330-1 material on raceways.
A computer model was developed based on AZEE transaction paper 57-660 by Neher,
- McGrath, and Buller to calculate the temperature rise in the conductor, heat generation per foot of raceway, and ampacity.
The model considers that all cables in the raceway were energized with the maximum steady state current.
A test program was developed to validate the computer model.
A series of test runs simulating representative as-built tray and conduit configurations, were conducted at the AEPSC Canton Test Lab.
The results of the tests validated the analytical computer model.
The testing was conducted under rigid laboratory controls, with test procedures, and with engineering supervision and review, however, it was not under the auspices of a 10 CFR 50 Appendix B quality assurance program.
The calculations using this computer that the original cable raceway sufficient margin to accommodate the resulting from wrapping raceways with model confirmed design included temperature rise Thermo-Lag.
3 ~
As discussed in 2(a)
- above, the identification and implementation of specific corrective actions is dependent upon the results of the NUMARC Thermo-Lag test program.
Cook Nuclear Plant is a participant in the NUMARC actions related to those corrective actions, if any, needed to resolve the issues identified by your request for information in item 2
above.
The specific test schedule for the NUMARC program will be provided to the NRC directly by NUMARC.
Compensatory measures have been taken in accordance with plant technical specifications.
These measures were described in previous responses to Bulletin 92-01 and Supplement 1.
Attachment 2 is a listing of the items which may be subject to corrective action.
We believe that these items are those addressed by your request from item 2 above.
We will provide'ou with a schedule for necessary corrective actions, if any, 120 days following completion of the NUMARC program.
ATTACHMENT 2 TO AEP:NRC:0692CK INSTALLED THERMO-LAG FIRE BARRIERS
~
PAGE I
APPENDIX R CONDUIT/CAOLK TRAY LIST (TSI XRAPPED)
UNIT RFC I IX:-]-2747 DC 2 24'12 DC 2-2415 CONDUIT MOT SMUTDONN Ul FLOOR MATC><KS I IA!-P2 LAL Cd IAI-CC
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LCC CCN CCN CCN CCN OM>4N 1$
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F IREZ LKNCTM REMARKS 5 MOOR RATING NALL 6 ROOF PER ARCHITECT TSL NOT ROOD GREEN TRAY CRKEM TRAY RED TRAY RED TRAY TRAY CDTS ENCASED IM CONCRETE PILAS CDTS ENCASED IN CONCRETE PILAS DC 2 24t4 6766R 2 174>R I 1746R I 9674R I 600CR I 16470 I 60040 2
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FOR CDTe 6504R I PACE C
UNIT RFC 2
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TRAY LEST FIREZ 65 65 4$
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REMARKS GREEN PILASTER GREEH PILASTER PILAS PILAS P ILAS P ILAS PILAS PILAS PILAS P ILAS PILAS PILAS
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5
PACE S
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UNIT RFC 2 DC-2 2)CO lOI 02
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HOUR RAT)NO MALL 2 ROOF