ML20002C403

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Forwards Request for Change to Tech Specs,Providing Enhanced Operability & Surveillance Requirements,Modifying Automatic Actuation Requirements for Spray Sys & Changing Allowable Operating Pressure Per 750725 ECCS Analysis
ML20002C403
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 05/10/1976
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20002C404 List:
References
NUDOCS 8101100258
Download: ML20002C403 (3)


Text

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CORSumCES Regulatory Docket Ejl!

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Company General Offices: 212 West M.chegan Avenue, Jackson. MacNgan 49201 e Area Code S17 788-0550 May 10, 1976 etIse

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DOCKET 50-155, LTCENSE DPR BIG ROCK POINT PLANT Transmitted herewith are three (3) executed ana thirty-seven (37) conformed copies of a request for a change to the Technical Specifications of License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 196h for the Big Rock Point Plaat.

1 This proposed change pro ~ ides enhanced operability and surveillance require-ments for the core spr4 systems, modifies the automatic actuation requirements of the containment spray systems such that the interlock between M0-706h cnd MO-7068 <an be eliminated, and changes the allowable operating pressure to be consistent with the ECCS analysis submitted July 25, 1975 Also attached is an analysis of ECCS performance for the case of a break in the ring core spray line assuming only reflooding from the nozzle spray system and feed-water system. This analysis shows that the core is never uncovered.

tLdf Av.a Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USNRC t

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DOCKET 50-155 t

REQUEST FOR CHANGE TO THE TECHNICAL SPECIFICATIONS BIG ROCK POINT PLANT i

For the reasons hereinafter set forth, the following changes.to the Technical Specifications of License No DPR-6 issued to Consumers Power Company on May 1, 196h for the Big Rock Point Plant are requested:

I.

CHANGES

. A.

Delete Section 3 5 2(a) in its entirety.

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B.

Delete Section 3 5 2(c) in its entirety.

C.

Delete ~;,he following phrasits from Section h.l.2(b):

", core spray and backup cere spray systems"

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" core spray system" and "and the fire water makeup system to the condenser hotwell" and

" core spray system and" oad "and the breakers for M07070 and M07071 r, hall be tagged 'open'"

D.

Delete Section h.2.l(a) in its entirety.

E.

Delete Section h.2.1(b) in its entirety.

F.

Delete the last sentence in Section 4.2.6.

l G.

In the table contained in Section 5 2.l(b), change the entry for the row now labeled " Maximum Reactor Pressure During Power Operation, Psig" to read as follows:

"Hominal Peactor Pressure During Steady 1331 1335 2

State Power Operation, Psig" H.

Delete Section 6.1.h(a) in its entirety.

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Delete Section 6.1.h(b) in its entirety.

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Delete Section 6.1.h(c) in its entirety.

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Change Section 6.1.5(b) to read as follows:

"The emergency condenser system control initiation sensors shall.be functionally tested not less frequently than once every 12 months."

L.

Delete Section 6.1.6 in its entirety.

M.

Delete the entries corresponding to " Post-Incident Spray S,/ stem -

Automatic Operation" in the table contained in Section 7 6.

'N.

Change the words " Reactor Emergency Core. Cooling System Trip Chcuits" i~

in the table in Section 7.6 to " Emergency Condenser Trip Circuits."

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Add a new Section 11 3 1.h as follows:

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