ML19341D122

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Forwards Fire Protection Review of Incomplete Items Identified in Fire Protection Safety Evaluation.Several Requirements Have Been Satisfactorily Resolved by Licensee Action Subsequent to NRC 800709 & 1124 Ltrs
ML19341D122
Person / Time
Site: Dresden 
Issue date: 02/10/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Abel J
COMMONWEALTH EDISON CO.
References
LS5-81-2-14, LSO5-81-02-014, LSO5-81-2-14, NUDOCS 8103041004
Download: ML19341D122 (5)


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Dear Mr. Abel:

Our initial Safety Evaluation Report (SER), dealing with fire protection at Dresden Unit No. 1, was issued on August 9, 1979.

In Section 3 of the SER, nineteen items were identified as incomplete and requiring further information from the licensee and evaluation by the staff.

We have completed our review of information dealing with these incomplete items as provided by Comonwealth Edison Company (CECO) responses dated August 2, August 31, and December 4,1979, and April 9,1980.

The results of our review were described in NRC's July 9,1980 and November 24, 1980 letters which identified completed items acceptable to the staff and unresolved items which required.further CECO action to satisfy NRC requirements.

Subsequent to the transmittal of our July 9, and November 24, 1980 letters, the staff has concluded that several items previously listed as requirements have been satisfactorily resolved by subsequent licensee action. provides the staff's evaluation of these items. provides a listing of the current status of all items identified by the staff as requiring CECO action during the fire protection review.

Sincerely, hOh Dennis M. Crutchfield Chief Operating Reactors Branch 49 Division of Licensing

Enclosures:

As stated cc w/ enclosures:

See next page e103041

Mr. J. S. Abel February 10, 1981 Cc t

Isham, Lincoln & Beale Director, Criteria and Standads Counselors at Law Division One First National Plaza, 42nd Floor Office of Radia?. ion Prograns Chicago, Illinois 60603 (ANR-460)

U. S. Environmental Protection Mr. B. B. Stephenson Agency Plant Superintendent Washington, D.C.

20460 Dresden Nuclear Power Station Pural Route #1 U. S. Environmental Protection Morris, Illinois 60450 Agency Federal Activities Branch U. S. Nuclear Regulatory Commission Region V Office Resident Inspectors Office ATTN:

EIS C0ORDINATOR Dresden Station 230 South Dearborn Street RR #1 Chicago, Illinois 60604 Morris, Illinois 60450 Resident Inspector Susan N. Sekuler Dresden Nuclear Power Station Assistant Attorney General c.o U. S. NRC Environmental Control Division Rural Route il 188 W. Randolph Street Morris, Illinois 60450 Suite 2315 Chicago, Illinois 60601 Morris Public Library 604 Liberty Stre '.

Morris, Illinois 60451 Chai raan Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Department of_ Public Health ATTN: Chief. Division of Nuclear Safety 535 West Jefferson Springfield, Illinois 62761 j

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9 ENCLOSURE 1 FIRE PROTECTION REVIEW ORESDEN 1 DOC)ET NO.50-010 Fire Detection Systems - Centrol Room. Section 3.1.l(1) i In the SER, it was our concern that a fire in the control room lower consoles may go undetected.

By letter dated April 8,1980, the licensee stated that no detectors are locatec in.the lower censoles in front of the stand up panels in the Centrol R com. The, lower censoles contain 3 safety systems - hign pressure core injection, core spray and the reactor protection system. The licensee stated that none of these safety systems are adjacent to each other and, consequently, a fire in ene panel would not propagate to another panel.

In addition, the

'icensee stated that with the control room being manned at all times, the operator could quickly detect fires to the lower consoles.

The licensee is installing an area detection system for the centrol room.

l' addi-tien, tne safe shutdown analysis has to demonstrate that the plant can be saf ely shutdown with the loss of the entire control room.

We conclude that with the installation of an area detection system, the licensee's fire detection for the control room meets the guidelines of Section F.2 of A;cer. dix A :o BTP APCSS 9.5-1 and, therefore, is acceptable.

Water Sucaression Systems. Secticn 3.1.5 In the.SER, it was cur concern that the licensee's fire su:pressicn systems fer several plant areas were not adecuate.

By let er dated Decemcer 4, 1979, the licensee cannitted to crovide sprinkler protec: ion for a numcer cf areas.

We infermed the licensee that the sprinkler systems crotecting the following areas were not acceptacle until the following mcdifications were made:

1.

Automatic Preaction Deluge System - cable penetratien area, a.

The design water flow should be 0.15 gallens per minute per square foot density on all cable tray surf ace areas, t.

Drawing #25-1734 Sheet 1 is not clear, piping cannot be traced, and the head location cannot be determinec.

c.

The feed for the preaction system for this area is fed frcm the pre-acticn system protecting the tunnels. This arrangement is not accept-able. The feed to the preacticn system fcr the caele spreading area shculd be an incecendent feed.

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2 I

d.

Heat collectors shculd be provided on the fusible linked spray heads, e.

Low air supervision should be orovided on the closed head spray piping with annunciation in the control rooms.

12. Automatic Deluge System - hydrogen seal oil unit.

a.

The density for the protection of the tank should be 0.25 gallons per minute per square foot over the entire surf ace area cf the tank.

(NFPA 15 paragraph 4-4.3.2b).

b.

A remote actuation station fer the deluge system should be located outside the entrance to the room.

3.

Automatic Preaction Deluge Systems - cable tunnel, a.

The spray heads should be located at the center line of the trays being protected, b.

Low air supervisien shculd be provided en the ciesed head spray piping with annunciation in the control room.

4 Extra Hazard Automatic Sprinklers - clean and dirty cil ror Density recuirements should be 0.2S gallon per minute per secre f act over the er.: ire ecom. This wiil then meet. the density recuirements of NFPA c13

ara;racn A2-2.1.2.5.

By le::er daked April 3,1930, the licensee cc=mitted c make the modifications statec acove witn the exceptien cf 1(c) and 3(b).

Re; arcing Item 1(c), one deluge valve is used to arm the creaction systems prc:ecting the tunnel and the cer.e: ration area. An alarm frcm either detec-icn systam wiil arm both systems. Fcr Item 3.(b), :ne low air supervisien cannot ce dene on this system since :ne tunnel is sucject to below freezing temceratures. To ensure the sys em is dry at all timec each riser has a drain noie at its low point.

The licensee's alternate mcdification regarding 1(c) woulc result in the cable penetra:icn area and cable tunnel automatic suppression systems being supplied by a single feed which is not acceptable. To meet Section E.3(a) of Appendix A to BTP APCSS 9.5-1, the licensee should provide an independent connection for each sprinkler system. The licensee's mcdificatien for Item 3(b) wculd result in a sy; tem whien would not meet the recommendations of NFPA 13 and, therefore, is not accectable. The licensee shculd provide low air supervisien on the c1csed head s; ray piping.

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ENCLOSURE 2 FIRE PROTECTION REVIEW STATUS DRESDEN 1 DOCKET NO. 50- 10 1

Item Descriotion Status

  • 3.1.l(1)

Fire Detection - Control Room C

2/10/81 3.1.1(2)

Fire Detection - Sphere Penetration C

7/9/80 3.1.3 Fire Water Pump R

11/24/80 3.1.5 Water Suppression Systems Sphere Cable Penetration Area Deluge System R

2/1 0/ 81 Sprinkler System - North Aux. Bay C

11/24/80 Water Deluge System - Hydrogen Seal Oil Area C

2/10/81 Water Spray Preaction System - Cable Passageway R

2 /1 0/ 81 Sprinkler Protection - Unit 1 Trackway, Laundry Storage and Welding Shoo C

7/9/80 Diesel Fire Pumo - Automatic Water Suopression System C

7/9/80 Core Soray -and -Post-Incident Pumo Areas - Automatic Water Suppression C

7/9/80 New Fuel Peceiving Area - Water Sprinkler System C

7/9/80 Clean and Dirty 011 Storage Room - Extra Hazard Sprinkler System C

2/1 0/81 3.2.1 Fire Detection System Tests R

11/24/80 3.2.2 Tech. Specs R

11/24/80 3.2.3 Fire Water System Feeds C

7/9/80 3.2.4 Excosed Structural Steel R

11/24/80 3.2.5 Emergency Condenser Valve R

11/24/80 3.2.6 Emergency Condenser Makeup R

11/24/80 3.2.7 Emergency Conden'ser Level Indication R

11/24/80 Fire Hazard Analysis R

11/24/80

  • C - Closed R - Requirement i