ML19269D631
| ML19269D631 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/01/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Reed C COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML19269D632 | List: |
| References | |
| NUDOCS 7906070385 | |
| Download: ML19269D631 (4) | |
Text
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May 1,1979 Docket No. 50-10 Mr. Cordell Reed Assistant Vice President Coamonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Reed:
We are reviewing the Dresden Unit No.1 Fire Protection Program submitted by your letters dated December 28, 1976 and March 29, 1977, and the Dresden Unit No.1 Fire Protection Safe Shutdown Analysis submitted by your letter of March 20, 1979.
To continue our review the additional information identified in Enclosure 1 to this letter is required.
To maintain our review schedule your response should be provided by May 31, 1979. is a copy of a trip report which describes the NRC Fire Protection Review Team's visit to the Dresden site on March 20-22, 1979. This report documents various Fire Protection ConTnitments and responses to NRC staff positions made by Commonwealth Edison personnel during the visit.
Please review the trip report and confirm the validity of these conmitments.
Sincerely, 5)W k b'
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Dennis L. Ziemann, Chief Operating Reactors Franch #2 Division of Operatir.., Reactors
Enclosures:
1.
Request for Additional Information 2.
Trip Report dated April 17, 1979 cc w/ enclosures:
See next page 2261 192 7906070 N [ [
Mr. Corcell Reed May 1,1979 I
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Isham, Lincoln & Beale Counselors at Law One First National Plaza. 42nd Floor Chicago, Illinois 60603 Mr. B. S. Stepnenson Plant Superintendent Dresden Nuclear Power Station Rural Route el Morris. Illinois 60450 U. S. Luclear Regulatory Commission ATTN-Jimmy L. Barker P. O. Box 706 Morris, Illinois 60450 Susan N. Sek.~er Assistant Atturney General Environmental Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Morris Public Library 604 LiDerty Street Morris. Illinois 60451
""q 2261 193
ENCLOSURE 1 REQUESTS FOR INFORMATION Part I 1.
The screen wash pumps are classified as safety-related by the licensee's submittal.
If this is the case, then the licensee should provide a 3-hour rated door between the diesel fire pump compartment and the screen wash pumps or provide an explanation of why the screen wash pumps are not necessary for a safe shutdown of the nuclear unit.
2.
The warehouse wall which faces the core spray puro is an unrated wall. The warehouse and its occupancy expose safety related cables in the warehouse associated with the core spray and post incident systems.
In addition the warehouse combustible loading seriously threatens the capabilities of the existing sprinkler protection.
The licensee should clarify what his intentions are for the warehouse in respect to its removal or redesign in terms of occupancy.
3.
The hose stations on the turbine mezzanine floor are not adequate to cover the area bounded by the column rows 21-28, D-H.
The licensee should provide hose stations or an evaluation which indicates that the area does not pose a hazard from the standpoint of fire damage to the facility.
4.
There are certain fire doors which are supervised and certain security doors which are also supervised. The security doors which also function as fire doors should be noted and a list provided to the staff.
5.
The licensee should submit a list of hose stations and systems which are required to be included in the technical specifications.,
6.
The licensee should either commit to the staff's training require-ment for the fire briode that each brigade receive quarterly drills and that no individual sha'il miss more than 2 drills /yr.
or provide justification for why this is not necessary Part II 1.
Staff Concern Water damage to safety-related load centers and switchgear from fire hose streams may render safety-related systems inoperable.
. Staff Position Water damage protection should be provided over MCC centers and switchgear which serve safety related functions for safe shutdown.
These include 480V switchgear 16 and 17 and MCC 25 and 26, 480V load center 14 and 15, power centers 19 and 20 and over the 125V dc panel west of 480V power center 19.
2.
Staff Concern The hydrants which are located on the unit 1 side of the fire water loop do not have 21/2" gate valves on the hydrant ports. This condition could require shutting the hydrant down in the event of necessity to replace hose during a fire and would interrupt hose stream protection for large flamable liquid hazards.
Staff Position The hydrants on the unit 1 side of the fire protection loop should be provided with 21/2" gate valves on the hydrant ports.
3.
Staff Concern Drains in flamable liquid areas are not provided with traps to prevent backflooding into other safety related areas.
Staff Position Drains in flamable liquid areas should be provided with traps.
2261 195
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ENCLOSURE 2 o
UNITED STATES y%
NUCLEAR REGULATORY COMMisslON 3..k.x 7. h I
WASHINGTON, D. C. 20555 m
e APR 1 7 1979
\\ +%-....o MEMORANDUM FOR:
D. Ziemann, Chief, Operating Reactors Branch #2, Division of Operating Reactors G. Lainas, Chief, Plant Systems Branch, Division p k THRU:
of Operating Reactors FROM:
L. Derderiari, Plant Systems Branch, Division of Operating Reactors
SUBJECT:
DRESDEN UNIT 1 FIRE PROTECTION REVIEW TRIP REPORT On March 20-22, 1979, the fire protection review team consisting of T. Dunning, L. Derderian and M. Antonetti visited the Dresden Unit 1 site. The purpose of this visit was to obtain first hand information on the physical separation of redundant safe shutdown equipment, the fire hazards and the fire protection features of the plant, to aid in the assessment of the adequacy of the plant's fire protection.
The review team examined all areas of the plant and identified the fire hazards and the fire protection features associated with each area.
Du' ring the site visit the ifcensee provided the review team with a written summary of modifications which he has proposed to implement.
This sunnary is presented in Enclosure 1.
During the closing meeting w1th the licensee, we discussed our positions developed 'during the site visit. Our positions and the licensees response indicated during the meeting are included in.
The questions and positions to which the licensee has not yet responded are included in Enclosure 3 parts 1, 2 and 3 respectively.
The licensee's response to a number of items indicated he would defer to the SEP program.
The ifcensee's responses to items 15, 16, 17 and 18 herein will be evaluated to_d m defferal is appropriate, and an a DUPLICATE DOCUMENT g
Entire document previously 226) 196 Nh O
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