ML17194A571
| ML17194A571 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/28/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17194A572 | List: |
| References | |
| 820229, IEB-80-06, IEB-80-6, LSO5-82-03-104, LSO5-82-3-104, NUDOCS 8204050288 | |
| Download: ML17194A571 (5) | |
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March 29, 1982 DISTRIBUTION Docket NRC PDR Local PDR ORB Reading NSIC
- DCrutchfield HSmith Docket Nos.
50-23;~
and 50-249 LSOS-82-03-104 Mr. L. O. DelGeorge
/
Director of Nuclear Licensing*
Commonweal th Edi son Company.
Post Office Box 767 Chicago, IL
- 60690
Dear Mr. DelGeorge:
OELD OI&E ACRS (10)
SEPB JHegner DVassallo ORB #2 Reading
SUBJECT:
COMPLETION OF NRC REVIEW OF BULLETIN 80-06, "ENGINEERED SAFETY FEATURES RESET CONTROLS AT DRESDEN STATION, UNITS 2 AND 3 We have completed our review of Commonwealth Edison's June'lO, 1980 "Response to I&E Bulletin 80-06" and ypur supplement thereto dated March 20, 1981.
The results of our review are discussed 1n the enclosed Safety Evaluation Report and our Contr,actor's Technical Evaluatio~ Report.
Based upon these reports, we have concluded that (1) Commo.nwealth Edison
.has satisfied the concerns of I&E Bulletin 80-06 and (2) that the engineered safety features-reset controls for the *Dresden Station Units No. 2 and 3 are 1n compliance-with NRC criter1a.
A post* implementation review of the installation and testing of the proposed modifications will be carried out by NRC to confirm the satisfactory completion of this topic.
Enclosure:
Safety Evaluation Report cc w/enclosure:
Sincerely, Original signed by Thomas V. Wambach. for/
Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
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NRC FORM 316 (10-60) NRCM 0240 OFFICIAL RECORD COPY.
USGPO: 1981-335-960
Mr. L. DelGeorg~
cc Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois. 60603 Mr. B. B. Stephenson Plant-Superintendent Dresden ~uclear Power Station Rural Route #1 Morris~ Illinois 60450 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.
20515 u *. S. Nuclear Regulatory Commis.sion Resident Inspectors Office Dresden Station RR #1 Morris, Illinois 60450 Mary Jo Murray *.
Assistant Attorney General Environmental Control Division 188 W. Randolph Street Suite 2315
~hicago, Illinois 60601 Chairman Board of Supervisors of
.:Grundy County Grundy*tounty Courthouse Morris,.Illinois 60450
- John F. Wolf, Esquire 3409 Shepherd Street Chevy Chase, Maryland 20015 Dr. Linda w. Little 500 Hermitage Drive Raleigh, North Carolina 27612 Judge Forrest J. Remick The Carriage House - Apartment 205 2201 L Street, N. W.
w.ashington, D.- c.
20037 Illinois Department of Nuclear-*Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 U. S. Environmental P*rotection Agency Federal Activities Branch.
Region V Office ATTN:
Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region Ill
- 799 Roosevelt Street Glen Ellyn, Illinois 60137
~
- e.
SAFETY EVALHATION REPORT DRESDEN STATION,- UNIT'S 2 AND 3 LICENSEE RESPONSE T~=l&E BULLETIN 80-06, ENGINEERED SAFETY FEATURES (ESF) RESET CONTROLS INTRODUCTION Instances have been reported at operating nuclear power plants where it had been found that following*_tfle reset of an ESF act1.1at~d ~ig.n?l, certain equipment, e.g., ventilation dampers, motors, and valves~ wouli:i return to its normal mode, which could compromise the protective _actions or the af-fected sys terns.
As a. result, on March 13, 1980, the NRC issued I&E Bulletin* 80,-06 requesting certain actions to be taken by licensees_ for ~11 PWR. and BWR facilities with* operating licenses.
EVALUATION The enclosed report (EGG 1183-4211) was prepared for us by EG&G, Inc., San
-Ramon, California as part of our technical assistance contractor program~*
It provides their technical evaluation of the licensee's response to I&E Bulletin 80-06 in accordance with NRC~provided guidance
- EG&G reported the licensee's conclusion that all safety related equipment remains in its emergency mode upon reset of the ESF actuating signal§.
However, they did identify the following seven cases where manual resets at the system 1 evel for valves and equipment may return: the. equipment to _-its normal operating status:*
(1)
Isolation coridenser valves l30J-l~ -2~ arid -4 (2)
PCIS group I valves (3)
HPCI system valves (4)
HPCI auxiliary oil pump (5). ADS system (6}
RPS system.
( 7)
ACAD/CAM. valves
The.licensee committed to complete design modification~ to items 1 and 2 above.
EG&G.reviewed these modifications and reported them technically satisfactory.
A post implementation review by NRC will confirm the successful installation and testing of these modifications.
The licensee offered justifications in lieu of corrective modifications for the re~aining five items (3, 4, 5, 6~ and 7).
EG&G did not evaluate th~se justifications *. The licensee :reported that the surveillance* tests~
which are performed at least at each refueling, provide detailed verification of system J ogi c and. operation from the process sensors to the actua.ting devices." Therefore, EG&G found the plant to satisfy the requirements of I&E Bulletin 80-06, with the exc.eption of items* 3; 4, 5, 6, and 7.
We have reviewed the licensee's justifications for not modifying the equip-ment *identified in these 5 items and find them acceptable on the following bases:
- . (3} * *HPCI *system*valves These valves remain in their emergency mode upon clearing of the initiating signal. Therefore, the design meets the intent of I&E Bulletin 80-06..* *
(4)
~nd.it is.no_ longer needed.
Hence, the design meets the intent of I&E Bulletin
- ao-06.
(5)
ADS System.
The ADS system is actuated under specific.
conditions at ~ time of low r~actor coolant inventory and has been analyzed for blowdown.
rate and loss of reactor coolant inventory.
Implementing manu~l resetting of each in-dividual ADS yalve would have an adverse effeci on ihe_blo~down rate.and the total loss* of reactor coolant inventory~ Reset**.*
. of the ADS *places it in*a standby mode, ready to be initiated as required.
CONCLUSION
.Y
- 3 (6)
RPS System Specific, intentional op~tatcir ~ction is*
required to re-withdraw the control rods.
Therefore, the design fulfills the intent of l&E Bulletin 80-06.
(7)
ACAD/CAM Valves.
These valves' are installed, but are out-of-service in the closed position.
Should the licensee desire to place th~se valves in s~rvice, in the future, the re-
. qui rements of I&E Bulletin 80-06 must be met.-
Based on the information and documen1;s provided by the licensee and on our I
- , ;~*
-revi*ew of the contractor' s*~report, we conclude that the license~ has sat is-*:
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fled the concerns of I&E.Bulletin 80-06, subject to a post implementation review of the successful inst~llation and testing of the indicated modifications by NRC.
Therefore, we find the ESF reset controls for the Dresden St~tJon, Unit Noi *. 2 and 3 to be in compliante with NRC criteria.
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