ML20215B802
| ML20215B802 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 06/09/1987 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ULNRC-1530, NUDOCS 8706170457 | |
| Download: ML20215B802 (7) | |
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~ a .1901 Gratiot Street, St. Louis Donald F. SchneII Vice President t June 9, 1987 U.S. Nuclear Regulatory Commission f Attn: Document Control Desk Washington, D.C. 20555 L Gent 2,emen: ULNRC-15 30 DOCKET NUMBER 50-483 CALLAWAY PLANT ANNUAL REPORT OF FIRE PROTECTION PROGRAM CHANGES l Pursuant to Section 2.C.5(e) of the Callaway Plant Facility Operating' License, NPF-30, Union Electric Company furnishes herewith the annual summary of changes made to the Callaway Plant t Fire.. Protection Program. Incorporated into this report are changes implemented from May 1, 1986 through April 30, 1987. These program modifications do not in any way decrease.the level' of fire protection at Callaway. If.you have any questions regarding the enclosed document, please' contact Mr. Reginald Allen at (314) 676-8853. I very truly yours, l Donald F. Schnell i JMC/ dis
Enclosures:
Annual Report of Fire Protection Program Changes i .1 fe"I8aNg;ggg;k,a go@ PD I I1 I i' j Maihng Address: P.O. Box 149, St. Louis, MO 63166
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-[. d t 0 STATE OF: MISSOURI - ). . )1 SS . CITY.OE ST. LOUIS -- ) - t... K -Donald F...Schne11', of lawful age,_being-first duly sworn upon oath.says'that'he is Vice President-Nuclear'and an officer of . Union Electric Company;-that he.has~ read the' foregoing document and knows ' the : content thereof; that he has executed the same for and' on.
- behalf L of.said company
- with full power :and authority.to.do'so; and-that;the facts'therein stated are true and correct to the:best of his knowledge, 'information' and belief.
/ By \\/ D5hald F. Schnell t. Vice. President Nuclear . SUBSCRIBED and sworn to b'efore met this day of 198 % ~ diL' h BARBAR b FA M k NOTARY PUBUC, STATE OF MISSOURl' klY COMMISSION EXPIRES APRIL 22,1983 . ST. LOUIS COUNTY l i.
~ i. a i 1 o. cc: Gerald Charnoff, Esq. Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W. Washington, D.C.. 20037 Dr. J..O. Cermak CFA, Inc. 4 Professional Drive (Suite 110) Gaithersburg,-MD 20879 W. L. Forney Division of-Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Misscuri.65077 Tom Alexion (2) Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 i l
j l bec: 3456-0021.6 Nuclear Date DFS/ Chrono l D. F. Schnell 1 J. E. Birk J.'F. McLaughlin j A. P. Neuhalfen R. J. Schukai M. A. Stiller-G. L. Randolph D. E. Shain H. Wuertenbaecher D. W. Capone A. C. Passwater R. P. Wendling T. H. McFarland D. E. Shafer D. J. Walker O. Maynard (WCNOC) N. P. Goel (Bechtel) G56. 37. (CA-460) Compliance (J. E. Davis) NSRB (Sandra Auston) i I a l l 1
p i ANNUAL REPORT { CHANGES TO THE APPROVED FIRE PROTECTION PROGRAM i UNION ELECTRIC-CALLAWAY PLANT FACILITY OPERATING LICENSE NO. NPF-30 -Listed below.in the form of Callaway FSAR Change Notices (CN) are all changes made to the approved Fire Protection Program at Union Electric's Callaway Plant i from May 1, 1986 through April 30, 1987. The approved Fire Protection Program is described in Sections 9.5.1, 9.5.2, & 9.5.3 of the FSAR. This report is being issued pursuant to Section 2.C.5(e) of the Callaway Facility Operating License No. NPF 30. CN 196
== Description:== ' Addition of a flammable liquids storage cabinet in'the Hot Machine Shop for the incidental storage of flammable liquids. I Supporting 'Information: The flammable liquids storage cabinet meets OSHA requirements, j has a capacity of 45 gallons, and is built in accordance with NFPA Standard 30. The addition of the cabinet allows for the i safe ~ storage of small arounts of various flammable liquids .used in the Hot Machine Shop operation. This change does not degrade the level of Fire Protection, but instead improves the handling and storage of flammable liquids and improves the i safe operation of the Hot Machine Shop. The Hot Machine Shop I is a non-safety related area and is separated from' safety related areas by a 3-hour, fire-rated wall. CN 293 l
== Description:== (Callaway Modification Package (CMP)-84-737) Installation of 4 additional emergency lighting in plant areas for illumir.ation j 4 of equipment required for safe shutdown in the event of an instantaneous Control Room fire and evacuation. Supporting Information: The emergency lighting system consists of individual sealed-beam, self-contained, battery units with an eight-hour capacity. All lighting units were evaluated for seismic II/I criteria where applicable. Routing of cables and conduits meets all separation requirements. This addition in no way degrades the Fire Protection Program, or any safety related system, or the safety of the plant. It improves the area lighting to better enable safe shutdown of the plant in the unlikely event of a Control Room fire and evacuation. i a i I t
l .-{a LCN 405' y
== Description:==
-(Request for Resolution.(RFR) - 02240 Rev. A) Revised description of plant-fire hose.in FSAR Appendix 9.5A, Section E.3(d).
Supporting-Information: The FSAR response to APCSB 9.5-1' Appendix A-regarding fire hose construction was too restrictive, only allowing polyester-jacket
- and1 neoprene-lined hose to be used. APCSP 9.5-1 Appendix A only
. requires.that. the jacket be woven and the hose be lined. This allows thefuse'of different constructions of fire hose that'are ~ now available, and for the use of any future advancements in fire hose construction. This change does not adversely impact the' ~ plant's Fire Protection Program. CN 416
== Description:== (CMP 84-0458) Addition of two thermal detectors in Auxiliary Building rooms 1305 and 1328. Supporting-lInformation: The addition of'these two detectors, which are not required by .l design', does not degrade the Fire Protection Program, or any 1 safety related system, or the safety of the plant. This change -improves the' Fire Protection' Program by enhancing fire detection. capability in the Auxiliary Building. 1 CN 421 f
== Description:== (RFR -'02239) Addition of the Reactor cavity refueling seal ring l gasket to the 2047.ft. elevation of the Reactor Building Fire Area ~RB-10. Supporting Information: Plant records indicate that the 2047 ft. elevation of the Reactor Building is the intended. location for the seal ring gasket -accarding.to the original design. The gasket only represents '855 BTU /sq..ft. of fire loading, which is a small increase to Pire~ Area RB-10. The gasket material is difficult to ignite and ~ there are no ignition sources in the area'during normal plant j operation. There is no' safe shutdown equipment in the area of the gasket. Therefore, this change does not decrease the level of Fire Protection. E 430L
Description:
' '(CKP 85-0229B) Upgrade the tendon buttress hatch covers to 3-hour, fire-rated covers. 4
.,4 Supporting Information: The tendon buttress hatch covers located on the 2026 and 2047 ft. elevation of the Auxiliary Building were originally constructed of checker plate steel. The checker plate alone is not a 3-hour, fire-rated barrier. This change upgraded these covers by adding fire retardant material to satisfy the 3-hour, fire-rated separation between fire areas A-8, A-16 and A-19. This change does not decrease the level of Fire Protection, but instead improves fire separation in the plant. CN 431
== Description:== Correct the definition of " negligible" as used in the Fire Hazard Analysis (FHA). I Supporting Information: The FHA interpretation of " negligible" was to identify only significantly measurable amounts of in-situ combustibles rather than simply measurable, as currently defined. Due to the defense-in-depth concept, the FRA is used as a tool to determine where combustible loading is or is not significant. Therefore, this change does not adversely affect the FRA or the Fire Protection Program. )}}