ML19248D617

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Amend 28 to License DPR-6,implementing NRC Fire Protection Position Re Shutdown Cooling Sys Isolation,Revising Requirements on Use & Testing of Fire Suppression Water Sys & Deleting Updated ECCS Tech Specs
ML19248D617
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 07/26/1979
From: Ziemann D
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19248D616 List:
References
FOIA-80-162, TASK-07-03, TASK-09-06, TASK-7-3, TASK-9-6, TASK-RR NUDOCS 7908170098
Download: ML19248D617 (8)
v • d • e


Text

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k UNITED STATES y;e g

NUCLEAR REGUL ATORY COMMISSION 3

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WASHINGTON. D. C. 20555 h

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CONSUMERS POWER COMPANY DOCKET NO. 50-155 BIG ROCK POINT NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. DPR-6 1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendmen*. by Consumers Power Company (the licensee) dated March 26,19).', complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License fio. DPR-6 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSI0f1 s

M" 1m m Dennis L. Ziemann,/ hief Operating Reactors Branch #2 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: July 26, 1979

ATTACHMENT TO LICENSE AMENDMENT NO. 28 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155

~

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages include the captioned amendment number and contain vertical lines indicating the area of change.

PAGES 4-6 11-1 11-2 11-4 11-5

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Uh g6 Change No. 26, 34, 8d, Amendment No. 70, Js, d'

1.l m i l. I ng Coiull t,l ona for OpernLlon Uni veillan< c IlequircinenL l 1. ').1. ls gilGKilCY C0llM C00I,Ifl0 SYSTEi4

11. l. l. li laatsitGEllCY CollE C00I, Illa SYSTEtt i

AppiicohiIiLy:

Applienhill Ly :

Appilen I.o the oper t.ing oLatus of the Applieu t.o periodic t.est,Ing requirement.a for t.he emerr,cocy core co>llng nyol.em.

emergency coro cooling nynLemn.

ObjecLive:

Obj ec t.1ve :

To annin e t.he capabil.ity of 1.he einergency

.To vertry opernbilit.y of 1, lie emergency core core coni 1ng nynLem t.o cool renet.or fuel 1n

, cooling nynt. cms.

l.he event. of n I.oun of Coolunt. Accident..

Spec t rienllon :

lipec i ri cn t.l on :

A.

Each mont.h the following shall be performed:

A.

The 1.wo core spray oyst.ema (or1 8 nnl ruol 1

Vert ry the opernbilit.y o;." 140-7051, -7061, -707t redundunL) nhall be opernble uhenever th

-7071 and -7066 by remote manual actunt. ion'. '.

pi n n t..lc in a power opernt. ion condi t.lon.

The original core apray oyalem shall n'ino I,enk t.co t,ing of the core spray heal exchtunter.

he opernble during rerueling operations.

omnLie act.unLlon or both fire pumpu.

The fire suppression system can be used for routine purposes without declaring the core veri fy t.hnt valve 140-7069 to locked or uented spray system inoperable provided total flow open poult. ton.

drawn from the system is limited to 400 gpm verify that the rire oyst.em t.rnnarormer deinge and provided such routine uses do not exceed

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30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> / year. The fire suppression system I" I

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can be used for fira fighting or for :.ests involving only flow through the fire vert ry Linit the hone required for hnchup coolI.

suppression system relief valves without unter to the core npray rectrenintion heni.

declaring the core spray system ini.perable exchanger la Installed on a deninnuted ench and without a flow and annual time restric-In i.he ucreenhounc.

tion.

II.

The ore upray rect roulallon nyntem phall be opernble whenever t.he plnnL in.in n power opernt.!on cond i t.lon.

C.

The core spray recirculnLlon heat lh exchnnger ohnll not he t.nken out. or h.\\

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nervice during power opernLlon for perioda exceeding four (Is) honru.

The hent exchanger ohn11 be conn _idered in-11-1 Amendment No. JD, JE, 28 y;

opernh~Ie und out, of ocrvj ce J T Lnhe

D burnile lenhuge exceeds 0.2 gpm.

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l.i mi t. i ng Condi t.lons for Opernt.lon Unryellinnee llequi rement.

11.1.l.h l:f1MluiKl4CY CollM COOI.If1G liY! ITEM (Cont.d) 11.la.l.h EMMitGMf1CY CollM CGGLlflG 11YliTFJi (ConLd)

D.

Iloth riie pumps (electric and dienel) and 11. At each major refueling outage, the following the piping nyulem t.o the core unray ayulem ahn11 he perronmed:

1. i e-i ns nha ll be operable whe;;.:w.r the allin n ion or core oprny uyut.em ut l.unLlon und p s un t.

in in a power operation cornlit. ion licensure aunt flow innLrumentnLion.

euni rerneling.

Vert ry t.lutt. l.he 1,vo core upray system cont.nin-.

M.

I f !!pec t rientions A,11, C and D nre not.

ment luolnLi n heck valves are not ot.uck ubut..

me t., n normal orderly ninitdown ohn11 be

nil. int.ed wi t.hin 234 hours0.00271 days <br />0.065 hours <br />3.869048e-4 weeks <br />8.9037e-5 months <br /> and the renet.or CallhrnLion or fire ayutem bunket, ut.rniner shall be shut. down as described in Sect.lon dirrerenLini pressure sulLchen.

1.2.';(n) wi thin twelve (12) honra and shut.

Opernbillt,y check or the core npray recircuin-down un dencribed in Section 1.2.$(n) und (h) within the following 2h hours.

Flo

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path, work nhal t be performed on the reactor or i tu conneeLed synt. ems when irra'inted fuel Verify manual and nulomat.ic actuation of the in in the rencl.or vennel which could core upray system valven MO-70S1, -7061, reunit. In lawering 1.he rencLor unter

-7070 ennt -7071 wi th water flow normal ly level he l iw elevnt. lon 610' 5".

blocked.

F.

Delet.ed.

Verify manual acLuntion of MO '(066.

Verify thnL the hone used for backup cooling G.

Inntrument net, poinLa ohnll be na t

e m my ncimMion IM

pecirled in Table 11.3.1.

exchanger in opernble anni t.ree or obvioun de fec t.n.

Perform n lenk check and flow check or the hnchup cooling water hone when connect.ed bel. ween the screenhouse fi re wat.er conneel.lon und 1.he core npray recirculut. ion heal 3 Mh ' '

\\

exchanger.

r 01 hh C.

InnLrumenta shall be checked, Leuted niul hik enlibrated at lennL nn frequently an linted in Table 11. h.1. h ( n ).

O' 11-2

-v_$

Amendment No. JD, 75,28

11ses:

The core spray system consists of two automatically actuated independent double capacity piping headers cap-able of cooling reactor fuel for a range of Loss of Coolant Accidents.

Either system by itself is capable of providing adequate cooling for postulated large breaks in all locations.

When adequate depressurization rates are achieved in the postulated small-break situation, either core spray systen provides adequate cool-ing.

For the largest possible pipe break, a flow rate of approximately 400 gpn is required after about 20 seconds.

Each core spray system has 100% cooling capacity from each spray header and each pump set. Thus, specifying both systens to be fully operational will assure, to a high degree, core cooling if the core spray system is required.

In addition, the primary core spray is required to be operable during refueling operations to provide fuel cooling in the unlikely event of an inadvertent draining of the reactor vessel. Water flow from the fire suppression system for fire suppression or for normal uses and testing for which the time and flow are restricted has a negligible effect on availability and is not a cause for declaring the systems inoperable.

The core spray systens receive their water supply from the plant fire systen.

The plant fire systen supply is from Lake Michigan via two redundant 1,000 gpm fire pumps, one electric and one diesel driven. These pumps start automatically on decaying fire system pressure.

If a passive failure of underground fire main piping should occur during the long-term cooling phase, the capability exists to bypass the affected portion of pip-ing utilizing a fire hose to ensure the continuation of long-term ECCS cooling.

The core spray recirculation system is provided to prevent excessive water buildup in the contoimnent sphere ano to provide for long-term, post-accident cooling.

The system consists of two pumps (400 gpm each) and a heat exchanger. The pumps take a suction from the lower levels of containnent and discharge to the core spray headers.

The systen is actuated manually when the wate-level in the containment rises to elevation 587 feet.

The 587-foot elevation will be achieved between 6 to 24 sours operation of one core spray and one containment spray system.

A test tank and appropriate valving is provided in the core spray recirculation system so the pump suction conditions and the flow characteristics of the system can be periodically tested.

One core spray recirculation pump has adequate capacity to provide fuel cooling at anytime following a Loss of Coolant Accident.

Continuous containment spray operation is not required during the post-accident recirc,lation phase if only one recirculation pump is available.

11-4 Amendment No. JS, 75,28 s

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