ML19318C293
| ML19318C293 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/25/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-80-06, IEB-80-6, NUDOCS 8007010313 | |
| Download: ML19318C293 (3) | |
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- 2. m D, m Genere A Offices: 212 West Michigan Avenue. Jackson, Michigan 49201. Area Code 517 788-0550 Jun>s 25,1980 f.r James G Keppler
)ffice of Inspection and Enforce =ent Region III U S Nuclear Regulatory Cc-rd.ssion 799 Roosevelt Road Glen Illyn, IL 60137 DOCKET 50-155 - LICE:ISE DPR BIG ROCK ?OINT PLANT - RESPONSE TO II BULLETIN 80 ENGDr:.,uED SAFITY FEATURE (ISF) RESET CONTROIS II Bulletin 80-06 dated March 13, 1980, requested Censu=ers Pever Cc=pany to determine if all associated safety-related equipment remains in its safety-related =cde upon the reset of the emergency featured actuation signal (ISFAS).
Cur response to this bulletin is as follows:
Action Recuested 1.
Review the drawings for all systems serving safety-related functions at the schematic level to deter =ine whether or not upcn the reset of an ISF actua-tion signal, all associated safety-related equip =ent remains in its emergency
=cde.
Response
1.
The actuation drawings for the following equip =ent have been reviewed:
a.
Pri=ary Core Spray Valves b.
Backup Core Spray Valves c.
Pri=ary Centai=ent Spray Valves d.
Reactor Depressurizing Valves e.
Centain=ent Autc=atic Isolation Valves f.
E=ergency Condenser Cutlet Valves Control Red Drives (scra= function) g.
h.
High Energy 3reak Ventilatien Da=per CV LO90 1.
Cff-Gas Isolation Valve All equip =ent except ite=s (e) and (i) meet the acceptable criteria based 00.
on the drawings. These two ite=s are discussed belev.
5 Contai=ent Aute=atic Isolatica Valves include valves in the ventilatien syste= vhich have dual autc=atic functions of isolation directly inhibit-fQ ing a radiation release, and an overriding function of opening for contain-cent high vacuu= to protect the contain=ent structure.
The circuit design B Ra. g g 3 g 3,3
~
Response to IE Bulletin 80-06 2
June 25,-1980 for opening by operator action following isolation closure presently meets the subject bulletin's criteria (refer to CPCo letter to the NRC dated Nove=ber 29, 1978). Since vacuu relief =ight te required following condens-ing of stea= during a LOCA, it would not be appropriate to modify this equip-
=ent to require manual switch action.
The off-gas isolation valve will return to the open position following a reduction of the high radiation initiating signal only if the trip reset on the initiating monitor is =anually reset. The off-gas isolation valve does not have a =anual centrol switch.
The original intent of this equipment, as stated in the FESR, Section 12.5.11, is to cause autcmatic shutdown in order to keep personnel exposure at acceptable li=its.
A=end=ent ik of the FESR dated June 27,1977, =cdifies the requirement to cause shutdown and substitutes greatly reduced radiation limits and ad=inistrative shutdown of the plant.
Thus, it is not dee=ed necessary to =cdify the circuit to prcride an addition-al reset feature.
Action Recuested 2.
Verify the actual installed instru=entation and controls at the facility are consistent with the sche =atics reviewed in Iten 1 above by conducting a test to de=onstrate that all equipment remains in its energency mode upon removal of the actuating signal and/or manual resetting of the various isolating or actuation signals. Provide a schedule for the perfernance of the testing in your response to this bulletin.
Response
2.
Verification of the actual iastru=entation and controls, as well as performance of a test of the ESF, to demonstrate that all equip =ent re=ains in its emerg-ency mode upon renoval of the actuating signal, will be conducted during the next refueling outage which is scheduled in late 1980.
Action Recuested 3.
If any safety-related equip =ent does not re=ain in its e=ergency =ede upon reset of an ESF signal at your facility, describe propcsed systen modifica-tion, design change, or other corrective action planned to resolve the proble=.
Response
3 Based en our review in Ite: 1, no =odifications are presently planned.
Action-will be taken only if our verification in Iten 2 is not satisfactory.
David ? Eoffman (Signed)
David ? Hoff an-Nuclear licensing Administrator l
CO Director, -Office of Nuclear Reactor Regulation i
Directer, Office of Inspection and Enforce =ent NRC Resident Inspector - Big Rock Point l
CONSUMERS PCWER CCMPANY
' Big Rcck Point Plant IE Bulletin 60-C6 Docket 50-155 License EPR-6 At the request of the Cc= mission and pursuant to the Atomic Energy Act of 195h and the Energy Reorganization Act of 1974, as a= ended, and the Cc= mission's Rules and Regulations thereunder, Consumers Power Cc=pany submits our response to IE Sulletin 80-C6, dated March 13, 1980, entitled, " Engineered' Safety Feature Reset Controls". Consumers Power Cc=pany's response is dated June 2h, 1980.
CONSUMERS PCWER CCMPANY 3y R C Youngdahl (Signed)
R C Youngdahl, Executive Vice President Sworn and subscribed to before =e this 25th day of June, 1960.
Linda K Carstens (Siened)
Linda K Carstens, Notary Public (SEAL')
Jackson County, Michigan My ec==ission expires June 10, 1981
.