ML20154P211

Application for Amend to License DPR-6,revising Tech Specs to Provide Clarification & Consistency by Reflecting Administrative & Editorial Corrections.Fee Paid

ML20154P211
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	09/21/1988
From:	Bordine T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20154P214	List: ML20154P211 ML20154P219
References
NUDOCS 8809300156
Download: ML20154P211 (4)

Text

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E' C011SumeIS Power pawrams AGEMEMr5 MISERr55 c.n.r.: ovm 1 ins w.n e.,n.o no.o. 2.a n, w 4erot . tem tas osso September 21, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - '

TECHNICAL SPECIFICATION CHANGE REQUEST - ADMINISTRATIVE / EDITORIAL CORRECTIONS' Attached is a request for change to the Big Rock Point Technical Specifications.

These proposed chances request administrative and editorial corrections to

provide clarification and consistency within the Technical Specifications.

i The attached Proposed Technical Specification Page Changes reflect previously submitted change requests which are still pending NRC action. Approval and l

issuance of these proposed changes should be coordinated with the previous 1

proposals dated December 30, 1986 and July 23, 1987 to ensure the issued pages do not contain inadvertent omissions or errors.

Pursuant to 10CFR170.12(c), a check in the amount of $150.00 is remitted with  !

this application.

,s+ k d.d l Thomas C Bordine l Administrator, Nuclear Licensing i CC Administrator. Region III. NRC NRC Resident Inspector - Big Rock Point 1

Attachment 1

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CONSUMERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications e License DPR-6 f i

For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Facility Operating License DPR-6, Docket l 50-155, issued to Consumers Power Company on May 1,1964, for the Big Rock  :

Point Plant be changed as described in Section I belowl  !

!. Chanae(s)  !

A. In Sections 4.1.2(c)1. and 4.1.2(c)2., change "... placed in the hot [

shutdown condition..." to "... SHUTDOWN as described in Section f 1.2.5(a)...".

t B. In Section 5.1.3(a), change "... control rod drive ..." to "... t control rod drives ..." and change "... power operation ..." to

" . . . POWER OPERATION . . ." .  ;

C. In Section 5.1.3(b), change "... scransning the control rod drive f

..." to "... scrasuming control rod drives ...". t i

D. In Section 5.2.3, change ". .. shall be 25% Akert. .." to ".. . shall  !

be 25% Akegg/k gr ...". t E. In Section 7.3.2(e), change ".. . CIC picoammeters..." to ". .. power range monitors..." and "...pleoammeters..." to "... power range  ;

monitor...".  !

F.

In Sections 7.4(f) and 7.4(l) change "... refueling operations..." to

. . . REFUELING OPERATIONS. . .".

[

C. In Sect ion 7.5. 7, change ". . . shutdown. . ." to ". . . SHUTDOWN. . ." and  !

insert the symbol "A" between 0.3% and k,gg/kett.

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H. In Administrative Controls Section 6.5.1.7, add "and i" betwaen "6.5.1.6.a. through d." and "above" in the paragraph following 6.5.1.7.c and capitalize all of the letters in "reportable event" in the second paragraph following 6.5.1.7.c.

l II. Discussion 1

These proposed changes are administrative in nature. They correct editorial errors, provide clarification of intent and consistency and capitalize defined terms (on pages where other changes are proposed) consistent with the practice in Standard Technical Specifications. The proposed changes are itemised below.

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l. _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ - _ _ _ _ _ _ _

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Change A clarifies the intent of the Specification. - Hot shutdown is .

not a defined operating condition for Big Rock Point. The general term "hot shutdown" means the reactor is suberitical and does not restrict reactor temperature. By Big Rock Point specific Technical Specification I definitions, this condition is equivalent to being shutdown as described in Section 1.2.5(a). This change also provides consistency ,

with other Technical Specification sections (e.g. 11.3.1.$, Action 3 and 11.3.3.4.8). -

Change B clarifles the intent of the Specification and capitalizes a "

defined term consistent with the practice in Standard Technical Speci fications.

. Change C clarifies the intent of the Specification.

Change D corrects an editorial error. 1 Change E cotrects the terminology for the neutron fluu measuring instrumention. This change was inadvertently not included in a

'tevious

, change request. The previous change was approved by Amendment 91 dated May 17, 1988, authorising use of the new power range monitoring instrumentation which was installed during the 1988 refueling outage.

Change F capitalizes a defined term consistent with the practice in i Standard Technical Specifications.

Change C capitaizes a defined term consistent with the practice in Standard Technical Specifications and editorially adds the delta symbol {

which was inadvertently omitted in a previous amendment.  ;

Change H clarifies the intent and provides consistency of what is allowed to be reviewed by the Plant Review Cossaittes via the routing j process. The routing review process was approved by Amendment 71 dated j Decembe r 10, 1984. The types of items reviewed by the routing process include procedure changes, technical specifica>. ion changes, tests or i experiments and modificational that is, items which generally require a  !

significant amount of time to understand and provide substantive {

comment. Categorically, the Site Emergency Plan and its implementing procedures f all into the types of items which are allowed to be reviewed under the routing process and should not be treated differently. This  :

change also capitalises a defined term consistent with the practice in  !

Standard Technical Specifications. {

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!!!. Analysis of Wo Sinnificant Hazards Consideration -

e All of these proposed changes are administrative in natute as they f correct an editorial error, provide clarification of intent and i consistency, and capitalize defined terms consistent with the practice j in Standard Technical Specifications. They do not involve modification ,

to any existing equipment, systems or components; change existing i administrative enntrols, or revise limitations on existing equipment.

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3 Therefore, these proposed changes do not create an increase in the probability or consequences of a previously evaluated accident.

Because these proposed changes do not involve any equipment modifications or revise any limitation on existing equipment, they do not create the possibility of a new or dif ferent kind of accident f rom those previously evaluated nor do they involve a reduction in a margin of safety. Consequently, these proposed changes do not involve a significant hazards consideration.

!Y. Conclusion The Big Rock Point / tant Review Committee has reviewed this Technical Specification Change Request and has determined this change does not involve an unreviewed safety question and, therefore, involves no significant hazards consideration. This change has also been reviewed under the cognizance of the Nuclear Safety Board. A copy of this Technical Specification Change Request has been sent to the State of Michigan official designated to receive such Amendments to the Operating License.

CONSUMERS POWER COMPANY By . __

David P Hoffran, Vice Prhs) - t Nuclear Operations Sworn and subscribed to before me this 21st day of September,1988.

.W1 LJ r LL -

Elaine E Buehrer, Notary Public Jackson County, Michigan My commission empires October 31, 1989 l

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