ML20087J237

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Forwards Rev 0 to Procedure LTS-1000-35, Fire Damper Operability Test
ML20087J237
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/15/1984
From: Schroeder C
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20087J239 List:
References
8286N, NUDOCS 8403220123
Download: ML20087J237 (2)


Text

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/ ' Common;ealth Edison

~ f Or.e First Nsticnal Ptara. Chicago, lilinois f

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\ ~J Address neply dr Post Office Box 767

\ ,/ Chicago.1:Imois 60690 March 15, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station, Units 1 and 2 Firs Protection NRC Occket Nos. 50-373 and 50-374 References (a): LaSalle County Station Unit 2 Facility Operating License NPF-18 (December 16, 1983).

(b): C.W. Schroeder letter to H.R. Denton dated November 23, 1983.

(c): Ins.pection Report Nos. 50-373/83-44 and 50-374/83-48.

(d): C. W. Schroeder letter to H. R. Denton dated March 13, 1984.

Dear Mr. Denton:

This letter and attachments were prepared in response to the following three items:

1) Reference (a) identified c~ondition 2.C (15)(h) which states:

Prior to exceeding five percent power, the licensee shall provide a surveillance program for NRC staff approval to ensure k operability of the fire dampers. This program will include a periodic operability test of a sample popultion of accessible dampers.

I

2) Reference (b) contained issue 8(b) which states:

1 Commonwealth Edison Company meets all current requirements of Appendix R and the Standard Technical Specifications regarding the operability surveillances of fire doors and fire dampers.

The NRC has a concern, however, that the current requirements may not be sufficient to assure operability of fire doors and fire dampers for the forty year life of the plant.

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8403220123 840315 g- l 1

\\ PDR ADOCK 05000 F L

H. R. Denton March 15, 1984 COMMlTMENT Commonwealth Edison Company agrees to develop a surveillance program to assure the long term operability of dampers. This program, which will include periodic operation of a sample population of accessible dampers, will be in place prior to exceeding 5% power and will be reviewed for technical adequancy by a fire protection engineer. Surveillances as a result of this program will be initiated prior to startup following the first refueling outage.

3) Reference (c) identified unresolved items 50-373/83-44-13 and 50-374/83-48-19 concerning this matter and referred them to NRR for resolution.

Reference (d) was submitted to address these three items and provided the program that Commonwealth Edison Company believes is the best technical approach to fire damper surveillances. On March 14, 1984, we were informed that NRR did not accept Reference (d) as fulfilling the License Condition 2.C.(15)(h). During discussions with Messrs. Novak and Vollmer at LaSalle County Station on March 14, 1984, it was determined that an additional technical moeting between NRR and the licensee to further address this and other fire protection issues would be useful.

Pending conclusion of further technical discussions and/or appeal action, the enclosed procedure LTS-1000-35 is provided to fulfill the requirements of License Condition 2.C.(15)(h) and supercedes our submittal of Reference (d). This procedure is provided for information only. Further revisions of this procedure will be controlled in accordance with the LaSalle Unit 2 Technical Specification Administrative section.

If there are any questions regarding this matter, please contact this office.

Enclosed for your use are one signed original and ten (10) i copies of this letter and the enclosure.

Very truly yours, C A i k ,1 ,s. u C. W. Schroeder Nuclear Licensing Administrator 1m cc: Dr. A. Bournia - Federal Express NRC Resident Inspector - LSCS 8286N

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