ML20235T898

Forwards Info Requested by Jj Harrison Re Upcoming App R Audit at Plant.Table 1 Summarizes Documentation Encl W/Ltr & Executive Sumary of Fire Protection Program Encl.Info for Items 1 & 7 Not Provided

ML20235T898
Person / Time
Site:	Quad Cities
Issue date:	07/23/1987
From:	Johnson I COMMONWEALTH EDISON CO.
To:	Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
3334K, NUDOCS 8710130273
Download: ML20235T898 (18)

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'?' #N l Commonwealth Edison

.* . j,~; . Ora First NItion7J Plan Chicago, Illinois

-3 v 7 Address Reply to: Post Office Box 767 a . (f L Chicago, Illinois 60690 - 0767 PR10RITY RO M g l-July 23, 1987

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fit Mr. A. Bert Davis Regional Administrator, U.S. Nuclear Regulatory Commission Region III

.799 Roosevelt Road Glen Ellyn, IL '60137

Subject:

Quad Cities Station Units 1 and 2 Transmittal of Appendix R Related Documents In Anticipation of Appendix R-Inspection NRC Docket Nos. 50-254 and '10-265

Reference:

Letter from J. J. Harrison to Cordell Reed dated April 17, 1987.

Dear Mr. Davis:

In response to the above referenced letter, Commonwealth Edison is providing to you at this time, information which was requested by your staff I in anticipation of the upcoming Appendix R audit at Quad Cities Station.

Table 1 summarizes the documentation enclosed with this letter and )

Enclosure 1 specifically lists this documentation. In order-to assist your -l staff, as well as those individuals who will be involved in the Appendix R 1 inspection, we have enclosed an executive cummary of our fire protection program (Enclosure 2).

Also b'eing provided is a set of the Quad Cities Safe Shutdown ]

Procedures. These procedures are in the process of being updated. A revised -

set will be forwarded to you when they become available. Additionally, the l Fire Hazards Report, Amendmenc 1, dated January 1986 and the Safe Shutdown i Report, Amendment 2, dated January 1986 are'also being provided for your use j in preparation for the audit.

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. Mr. A.B. Davis ' July 23, 1987 i

It should be noted, however', th'at Quad cities Station does not have a. i reactor coolant pump. Therefore, we do not have need for a reactor coolant l pump oil collection system. For these reasons, we are not providing the l

.information as requested in Items Number 1 and 7. l Should any additional information or clarification be required, please f contact this office. 1

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.5 Very.truly urs, I. M. Johns n

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Nuclear Licensing A istrator' 1m ]

1 Enclosures cc: T. Ross - NRR (w/o Att.) R J. Holmes- l l

Quad Cities Resident Inspector (w/o Att.)'

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QUAD CITIES STATION UNITS 1 & 2 TABLE 1 DESCRI PTION OF I NF ORMAT ION- PROVI DED r3

- 1) Piping and Instrumentation Diagrams for Hot and Cold Safe Shutdown Systems ( current):

M-22 M-58 M-81 M-37 M-69 M-89 M-39 M-70 M-50 M-79

2) The, following plant layout and equipment locations drawings:

o F-X-2 Drawings Cable routing and equipment locations for hot shutdown RHR Division I Shutdown me t hod o F-X-3 Dr awing s Cable routing and equipment locations for i hot shutdown RHR Division II Shutdown l method l

l o F-X-4 Drawing s Cable routing and equipment locations for hot shutdown RCIC method o F-X-5 Drawing s Cable routing and equipment locations for Hot Shutdown Safe Shutdown pump method o F-X-6 Drawing s Cable routing and equipment locations for -

cold shutdown RHR Division I method o F-X-7 Drawing s Cable routing and equipment locations for Cold Shutdown RHR Division II method

The above drawings were issued in November of'1984 and updated in October of 1985. The 1985 update added additional safe shutdown equipment. The cable routings on these drawings reflect the condition of the sta tion prior' to the 1982 and 1984 Appendix R modifications. None of the cable reroutes or alternate feed modification described in Section ,

6 of the Safe Shutdown Report' have been included on these i drawings , except for installation of t'ae safe shutdown pump.

3) The Exemption Requests, Appendix C, provides a sketch of the a Unit 1 and Unit 2 redundant Residual Heat Removal Division I and Division II cable routings in the Reactor Building" . '

Basement. In addi tion , drawi ngs F-2-1, F-9 -1,' and F-14-1 show fire wrap locations. >

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QUAD CITIES STATION

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UNITS 1&2 TABLE 1 (Cont'd)

4) Current electrical schematics and single lines are being provided for all safe shutdown components. These schematics have been grouped by safe shutdown path. . Simplified single J

,- line AC and DC diagrams are provided in Section 3 of the Safe l Shutdown Report. , j

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S/;, Plant layout drawings ~ identifying; fire suppression,. fire dyrection, fire wrap and_ fire barriers (F-X-1). These drawings were revised in January 1985, October 1985, and May 1987 to incorporate the recent modification work.

g. 6) Marked up plant layout drawings which identify geceral locations o,f emergency lighting units (F-X-8). These drawings &were revised to: incorporate recent modification' 1 work.

7) Plant operatirN Lprocedures- will be prov.lded ~ by Quad Cities Station. '

8) Fire damage control and repair procedures will be provided by Qand Cities Station.

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9) The updatad SSD Report and Fire' Hazards Analysis (dre included.

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i ENCLOSURE 1  ;

i List of Documents l l

1. P&ID's  !

i M-22 (S hee t 2), Rev. B l M-3 7, Rev. AC M-3 9 (S hee t 1 of 2), Rev. AJ  ;

M-39 (Sheet 2 of 2), Rev. AJ M-50, Rev. AC M-58 (Sheet 1 ), Rev. AE M-69 (S hee t 2), Rev. C M-70, Rev. G M-7 9, Rev. U i M-81 (Shse t 1 of 2), Rev. AF MO S1 (Sheet 2 of 2), Rev . A K .

M-89, Rev. T l

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ENCLOSURE 1 List of Documents (Cont' d)

2. Plant layout, equipment locations, and cable routing drawings F-2-2, Rev. B F-11-2, Rev. B F-2-3,-Rev. B F-11-3, Rev. B F-2-3, Rev. B F-ll-4, Rev. B F-2-4, Rev. B F-ll-5, Rev. B F-2-5, Rev. B F-11-6, Rev. B F-2-6, Rev. B F-11-7, Rev. B F-2-7, Rev. B F 2, Rev. B l F-3-2, Rev. B F-12-3, Rev. B F-3-3, Rev. B F-12-4, Rev. B F-3-4, Rev. B F-12-5, Rev. B l F-3-5, Rev. B F-12-6, Rev. B F-3-6, Rev. B F-12-7, Rev. B l F-3-7, Rev. B F-13-2, Rev. B j F-4-2, Rev. B F-13-3, Rev. B F-4-3, Rev. B F 4 , Rev. B l

l F-4-4, Rev. B F-13-5, Rev. B F-4-5, Rev. B F -1 3-6 , Rev. B F-4-6, Rev. A P-13-7, Rev. B  ;

F-4-7, Rev. A P-14-2, Rev. A i F-5-2, Rev. B F-14-3, Rev. A l F-5-3, Rev. B F 4 , Rev. A F-5-4, Rev. B F-14-5, Rev. A F-5-6, Rev. B F -1 4 - 6 , Rev. A j F-5-7, Rev. B F-14-7, Rev. A ]

F-8-2 (S he e t .1 of 2), Rev. A F-15-2, Rev. A l F-8-2 (Sheet 2 of 2), Rev. A F-15-3, Rev. A I F-8-3 (Sheet 1 of 2), Rev. A F-15-4, Rev. A F-8-3 (Sheet 2. of 2), Rev. A F-15-5, Rev. A F-8-4 (Sheet 1 of 2), Rev. A F-15-6, Rev. A F-8-4 (Sheet 2 of 2), Rev. A F-15-7, Rev. A F-8-5 (Sheet 1 of 2), Rev. A F-17-2, Rev. B F-8-5 (Sheet 2 of 2), Rev. A F-17-3, Rev. B F-8-6 (Sheet 1 of 2), Rev. A F 4 , Rev. B F-8-6 (Sheet 2 of 2), Rev. A F-17-5, Rev. B .

F-8-7 (Sheet 1 of 2), Rev. A F-17-6, Rev. B l F 7 (Sheet 2 of 2), Rev. A F-17-7, Rev. B {'

F-9-2, Rev. A F-18-2, Rev. B F-9-3, Rev. A F-18-3, Rev. B F-9-4, Rev. A F-18-4, Rev. B F-9-6, Rev. A F-18-5, Rev. B F-9-7, Rev. A F-18-6, Rev. B F-10-2, Rev. B F-18-7, Rev. B F-10-3, Rev. B F-19-3, Rev. B F-10-4, Rev. B F-19-4, Rev. B F 6 , Rev. B F-19-7, Rev. B F-10-7, Rev. B l l l

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. ENCLOSURE 3, List of Documents - (Cont'd)

3. Appendix R Exemption Request ^(one volume)

4. Single Lines and Schematics by SSD Path (see pages 5 through "

8'of this enclosure)

5. The following layout drawings identifying Fire Protection: j F-1, Rev. E F-5-1, Rev. )

F-2-1, Rev. D F-8-1, Rev. E {

F-3-1,.Rev. D- F-10-1, Rev. C 1 F-4-1,-Rev. D F-ll-1, Rev. E j F-9-1, Rev. E F-16-1, Rev. C i F-12-1, Rev. E F-19-1, Rev. C i F-13-1, Rev. F F-20-1, Rev. C F-14-1, Rev. E F-21-1, Rev. C F-15-1, Rev. E F-22-1, Rev. C  :

F-17-1, Rev. E F-23-1, Rev. C F-18-1, Rev. E F-24-1, Rev. C

6. Emergency Lighting Drawings ,

F-201-8, Rev. C ,

F-202-8, Rev. C F-203-8, Rev. C F-204-8, Rev. C F-205-8, Rev. C F-206-8, Rev. C ,

F-207-8, Rev. C F-208-8, Rev. C F-209-8, Rev. C F-210-8, Rev. C F-211-8, Rev. C F-212-8, Rev. C 7A. Updated Fire Hazards Analysis (one volume) 7B. Updated Safe Shutdown Report (one volume) l 4

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ENCLOSURE l-L

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STATUS DWG'NO. REV REV DATE: ~OR CODE .j

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4E-1307A B 048E85 .X- j 4E-1310 W 05 NOB 5' X- l 4E-1311 AC 05 NOG 5 X .I 4E-1312 N 01AP86 X

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STATUS  !

DWG NO REV REV DATE OR CODE  !

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4E-1419 W 25MA86 X

'4E-1430 1 AK 17FE87 X-  :

4E-1430 2 AK 17FE87 X  !

4E-1438C- W 15MY85 X  :

4E-1438D J 28AUB4 X. ]

4E-1438E W 15-Y85 X i 4E-14380 T 20MA86 X j 4E-1438J- 1 V 27DE85 X.

4E-1438J- 2 V 27DE85 X 4E-143BJ 3 V 27DE85' X' 4E-1438K 1 N 23DE85 X 4E-143BK- 2 N' 23DE85 X 4E-1438K 3 N 27DE85 X' l 4E-1438L 1 V 23DE85 X ]

I 4E-1438L 2 V 27DE85 X- f l

4E-143BL 3 V 23DE85 X-4E-1438M '1 Q 05MYS6- 'X 4E-1438M 2  ? 23DE85 X 4E-1438M 3 N '23DE85 X 4E-1438P M 308E85 X-4E-1438G M 308E85' X 4E-1438R H 01AP86 X l 4E-1438S H' 01AP86 X 4E-1461 AE 308E85 X 4E-1461A A 210C82 4E-1462 Z 1BNOS5: X -

4E-1464 W 22MYS6 , X 4E-1484B Z 10JA86 X L

4E-1484C T 21MY85- X' 4E-1484D Y 22MYS6 X 4E-1484E 1 0 22AP86 X i 4E-1484E 2 0 22AP86 X l 4E-1484F 1 0 07AP86 X 4E-1484F 2 Q 07AP86: X 1

4E-1490 H 10MYB3 X f 4E-1493 U 15AUB6 X 1 l 4E-1527 1 B 15AP87. X

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4E-1527 2- B 2OJA87 X 1 4E-1527 3 B 15AP87 X' l 4E-1591 K 068E84' X ]

4E-1676C N 308E85' X -(

l 4E-1679F G 01MY86. X 4E-1685C C 1-&E85 X 4E-2301 S 25MABS- X .,

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4E-2306 R 22MY86 .X l

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.DWO NO REV REV DATE OR CODE

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4E-2310 W 01NOO5 X 4E-2311 U 01NO85 X 4E-2312 S 01 NOB 5 X 4E-2315 0 140C85 X 4E-2317 1 P 010C86 X 4E-2317 2 .P 010C86' X 4E-2317 3 P 010CB6 X 4E-2318 1 Y 178E86 X 4E-2318 2 Y 17BE86 X 4E-2318A E 17SE86 X 4E-231BB B- 02DE85. X 4E-2320 T 16DE85 X 4E-2321 L 10AUB4- X 4E-2342. R 140C85 X 4E-2343 N 140C85- X 4E-2344 1 A 30MYB6 X-4E-2344 2 A 30MYS6' X 4E-2344 3 A 30MYB6 X l

4E-2344 4 A 30MYB6 X 4E-2346 V 080&S6 'X 4E-2346A A 05FE85 X 4E-2349 1 M 010C86 X 4E-2349 2 M 010C86 X 4E-2349 3 M 010C86 X 4E-2350A U 22MYB6 X 4E-2350B T 22MYB6 X 4E-2350C E 27DE85 X 4E-2389A B 15 JUS 4 X 4E-2389B C 15JOS4 X 4E-2393 N 17SE86 X l

4E-2417 N 09MA84 X' 4E-2418 G 11N085 X 4E-2419 AC 12AUS6 X 4E-2430 V 22MYB6 X 4E-2438C 1 G 13JA87 X 4E-2438E 1 0 08JA87 X 4E-24380 I SM R

24FE86 X 4E-2438J 2Y K 03FE86 X 4E-2438J 2 L 118E86 X 4E-2438J 3 K 03FE86 X 4E-2438K 1 C 03FE86 X 4E-2438K 2 0 03FE86 X 4E-2438K 3 0 03FE86 X 4E-2438L. 1 L 03FE86 X 4E-2438L 2 M 118E86 X 4E-2438L 3 L 03FE86 X 4E-2438M 1 H O FE86 X l

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4E-2438P 1 J 240C86 X 4E-2438P 2 J 240C86 X 4E-2438G 1 K 240C86 X 4E-2438G 2 K 240C86 .X  :

4E-2438R F 01AP86 X 1 4E-24388 F 01AP86 X 4E-2461 Y 17MA86 X 4E-2461A A 25AP83 X 4E-2462 1 W 30APB7 X. -l 4E-2462 2 W 30AP87 X '- !j 4E-2462A A 25AP83 X j 4E-2464 N 22MYS6. X 4E-2484B W 30AP85 X 4E-2484C R 09JYS6 X 4E-2484D g - -- R 13DE85 X 4E-2484E--

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ENCLOSURE 2 QUAD CITIES STATION FIRE PROTECTION PROGRAM EXECUTIVE

SUMMARY

QUAD CITIES STATION FIRE PROTECTION PROGRAM '

EXECUTIVE

1.0 BACKGROUND

2.0 10CFR50, APPENDIX R COMPLIANCE 3.0 REEVALUATION OF CECO APPENDIX R COMPLIANCE 4.0 SAFE SHUTDOWN PROCEDURES

5.0 REFERENCES

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QUAD CITIES 1&2 FIRE PROTECTION PROGRAM

1.0 BACKGROUND

As part of the continuing NRC evaluaticn following the fire at the Browns Ferry Nuclear Station in March 1975, Commonwealth Edison Company (CECO) has outlined its fire protection program and features at Quad Cities Power Station in a number of documents submitted to the NRC between 1976 and the present.

The document entitled, "Information Relevant to Fire Protection Systems  !

and Programs - Parts 1-2. April 1977," provided CECO's response to the NRC initial request for a comparison of the fire protection provisions of Quad Cities Station with the guidelines of Appendix A to BTP 9.5-1. This was CECO's first Fire Hazards Analysis of Quad Cities Station and resulted in l a number of fire protection modifications. This Fire Hazards Analysis has been updated to reflect the current station configuration and is enclosed.

l CECO also responded to NRC guidelines regarding nuclear power plant fire l protection programs issued in the following documents:

1. Supplementary Guidance on Information Needed for Fire Protection Evaluation, September 30, 1976,

2. Sample Technical Specifications, June 24, 1977, and

3. Nuclear Plant Fire Protection Functional Responsibilities, Administra-tive Controls, and Quality Assurance, August 12, 1977.

Following the review of these CECO submittals and a plant inspection, the NRC staff docketed a Fire Protection Safety Evaluation Report (FPSER) for Quad Cities Units 1 and 2 in July 1979. I Implementation of these guidelines resulted in additional fire protection measures being incorporated to enhance the existing fire protection program and satisfy the NRC defense-in-depth philosophy. Many studies and much dis-cussion were also associated with the subsequent NRC fire protection guide- 1 lines and requirements.

2.0 10CFR50, APPENDIX R COMPLIANCE The fire protection rule, Appendix R of 10CFR50, was issued on February 19, 1 1981, for Quad Cities Units 1 and 2. At that time,the shutdown analyses and subsequent related correspondence for Quad Cities Station was well ,

underway and being reviewed by the NRC staff. CECO continued to provide the NRC staff with all necessary information for their review of the station's safe shutdown capability.

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, QUAD CITIES 1&2 On July 1,1982, CECO submitted the final response and position in Generic Letter 81-12 questions, Safe Shutdown Capability, Associated Circuits, and a listing of the exact shutdown methods and necessary safe shutdown modifi-cations for Quad Cities Station. Submitted with this enclosure was Quad Cities Station's Fire Protection Associated Circuits Analysis and Modifica-tions Report. The cable discrepancy report was revised and resubmitted August 16, 1982, as a supplement to the Modifications Report. The follow-ing modifications resulted from this analysis:

Alternate Feeds Isc' nion and Local Control SSD Pump Reroutes Enclosure D of the July 1,1982 submittal included the first formal exemp- l tion request from the requirement of Appendix R Section III.G.3.b for fixed fire suppression. This request was made for nine fire zones having electrical equipment critical to the power distribution necessary for normal and emer-gency operation of safety-related equipment for Units 1 and 2 at Quad Cities.

A formal exemption was granted from the requirements of Section III.G.3 on June 23, 1983.

By cover letter dated December 30, 1982, the NRC staff stated that they had completed the review of Quad Cities 1 and 2 alternate shutdown capability which is used to achieve safe shutdown in the event of a fire. This capa-bility was evaluated against the requirements of Sections III.G and III.L of Appendix R to 10CFR50. Based on this review, the NRC staff concluded that Quad Cities 1 and 2 was in compliance with Appendix R Items III.G.3 and III.L regarding safe shutdown in the event of a fire. A Safety Evalua-tion Report (SER) was written on this Appendix R review. The conclusion of this evaluation states:

"We (the NRC staff) have reviewed the licensee's proposed alternate shutdown capability for certain designated areas in Dresden Units 2 and 3 in accordance with Appendix R criteria. Based on that review, we conclude that the performance goals for accomplishing safe shut- I down in the event of a fire, i.e., reactivity control, inventory i l control, decay heat removal, pressure control, process monitoring, I and support functions are met by the proposed alternate in these areas. Therefore, we conclude that the requirements of Appendix R l Sections III.G.3 and III.L are satisfied in the areas identified in Section 2.2 of this Safety Evaluation."

On the basis of these conclusions, CECO management was confident that the intent of Appendix R has been satisfied and continued working to implement the identified modifications-in accordance with 10CFR50.48 (c) (4).

On October 19, 1983, Generic Letter 83-33, which reemphasized NRC positions on certain requirements of Appendix R, was transmitted to Quad Cities 1 and

2. As a result, CECO management decided to perform a reevaluation of the previous analysis to verify that misinterpretations did not exist.

QUAD CITIES 1&2 3.0 REEVALUATION OF CECO APPENDIX R COMPLIANCE  ;

3.1 PURPOSE CECO management requested that a detailed, independent outside review of its entire fire protection program be conducted at Quad Cities. The study was to compare the criteria of Appendix R, with .particular attention given to the latest NRC staff positions as presented in Generic Letter 83-33, with the previous Appendix R analysis.

3.2 REEVALUATION TEAM In October 1983, CECO contracted the services of Professional Loss Control, Inc. (PLC) to conduct an in-depth reevaluation at Quad-Cities Station. PLC was selected to perform this review because of their extensive involvement in all aspects of nuclear power 1 plant fire protection. Ceco also contracted the architectural engineering firm, Sargent and Lundy (S&L), to provide the tech-nical support necessary for evaluation of mechanical, electrical, )

and nuclear systems at the station. {

3.3 METHODOLOGY OF REEVALUATION The Appendix R reevaluation included the detailed review of the j fire protection program and safe shutdown analyses for Quad Cities

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Station Units 1 and 2. The fire protection program was reviewed and evaluated not only against Appendix R requirements but also included previous station commitments made in the:

Fire Hazards Analysis

. Responses to Supplementary Guidance, August 12, 1977, i Nuclear Plant Fire Protection Responsibilities, Admin-istrative Controls and Quality Assurance

. Fire Protection Safety Evaluation Report (FPSER)

Station Technical Specifications

. NFPA Fire Codes (Design, installation and maintenance of fire protection systems) 1 Related Correspondence with the NRC The adequacy of the 1982 safe shutdown analyses and related correspondence was verified and revalidated. These CECO responses were reviewed to the latest NRC staff positions and the criteria of Appendix R. Special atten- j tion was given to the issues addressed in Generic Letter 83-33. l i

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QUAD CITIES 1&2 A careful review was conducted against the guidance of Appendix R Sections III.G and III.L and Generic Letter 83-33. This review revali-dated the Associated Circuits Analysis of June 1982 and expanded the analysis to demonstrate that a fire in one fire zone would not adversely affect the ability to shut down the plant even with alternate shutdown equipment located in an adjacent fire zone.  ;

Documentation of the modifications and justification of Appendix R exemptions identified in this review are contained in the December 18, l 1984 submittal, " Interim Compensatory Measures and Exemption Requests." .l These modifications included:

Fire Detection 1 Fire Suppression Upgrades to Fire Barrier 4

Emergency Lighting A revised Appendix R Safe Shutdown Report (Enclosure 1) was prepared which updated and replaced the Associated Circuits Analysis of June 1982. This report will document in detail the methodology and results of the reanalysis including hot shutdown, cold shutdown, potential adverse spurious operations, emergency lighting study, and the structural steel analysis. Documentation of the NFPA code study and the previous commitment review will be available for review.

The Safe Shutdown Report is being revised to incorporate recent modification work. In addition, several sections are being revised to clarify and sub- .

I stantiate Quad Cities Station Compliance with Appendix R. This includes ]

clarification of several 1982 Safety Evaluation Report discrepancies (see Reference (4)). All changes to the SSD Report shall be clearly 16entified -;

so as not to impede your review. None of the changes made will deviate from the current safe shutdown approach.

l CECO personnel also recognized the need to consider compensatory measures  !

l when 10CFR50.48 (c) (4) could not be satisfied. Those proposed modifica-  !

tions which will not be completed according the the 10CFR50.48 schedule )

have been considered to determine the impact of a fire in the area before completion of the modification. Discussions are included in the December 18, 1984 submittal.

l In addition, F-Drawings were developed to document various aspects of the  !

Fire Protection Program as follows:

l F- X- 1 - Identify Suppression Detection, Fire 3 (Enclosed) Wrap, and Fire Barriers (Current) l F-X-2 through 7 - Identify SSD Equipment and Cabling (Enclosed) Locations (Record 1984) )

• e OUAD CITIES 1 and 2 F-X-6 - Emergency Lighting Drawings (Current)

(Enclosed)

F-41 through 198 - Fire Rated Barrier Sections and Schedules (current) 4.0 SAFE SHUTDOW PROCEDURES Safe Shutdown Procedures are enclosed. Currently, these procedures.are in revision to incorporate suggestions from the operators and consultants.

Any changes made to the procedures will be clearly identified at the time of the audit so as not to impede your review. The timeline for accomplishing manual actions has been reanalyzed. The reanalysis has resulted in increasing the time necessary to establish reactor water makeup to 30 minutes.

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