ML19345E435

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Submits Info That Describes Design & Installation of core-flooding Connection & General Procedures to Be Used for Operation
ML19345E435
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/07/1968
From: Haueter R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101190252
Download: ML19345E435 (7)
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'- I % ~. b~I w Regulatory Suppl Fife Cy. r CODSilmBIS L ;(A.f I P000f Company anne,ai on.c ce 2 2 w.,e u,c n..pn Avenue. Jac ksort. M.c hig.in 4'4201. Are t Code S17 7 A8 0550 March 7, 1968 TD .cNih ' S s i \\ 'l \\ Dr. Peter L. Morris, Director -gI,, r.?"o# _~ Division of Reactor Licensing 4 ',,, /g-- 77 U. S. Atcmic Energy Commissica \\ ;'. s 'Q Washington, D. C. 20545 N' g

Dear Dr. !* orris:

Attention: Mr.1. J. Skovholt In proposed change I?o.13 to the Big Roch Point Technical '3pecifications, Docket No. 50-155, dated I'ay 26, 1967, Consumers Power Ccmpany requested permission to install six high performance developmental fuel bundles in the Big Rock Point reactor. Approval by ACRS vas contingent upon the installation of a temporary connection to permit flooding of the reactor core in the event the existira core spray line was severed. This informtional letter describes the design and installation of this core-flooding connection and the general procedures to be used for 'to operation. At this writing, a four-inch supplementary core flood line has been installed. The auxiliary core flood line confo ms in general design to the present core spray cooling line. This flood line connects the high pressure feedvater line at the reactor fe-d pump discharge to the fire water hender. The line is a four-inch diameter ASTM A-106 Grade B ceanless steel pipe - with a schedule 40 rating from the fire water header to the first valve (see attached Fig. I). The reminder of the line is rated at schedule 160. The two manually operated four-inch cate valves and the check valve are rated at a preccure of 900 psi at a temperature of 850 F. The3/4-inchvalvesinthetelltalelines are rated nt 1500 psi. The telltale valve nearest the feedvater 2.ine vill namn,lly be closed. This valve vill permit the check valve to be testel periodically. M y The other telltale vill be norm 11y open to monitor f s ,[ \\ 'S for Icaknre of water through the valves. Fnd capc on the telltale / M

V.q),f lines vill have 1/16-inch diameter holes.

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.___y.,. () Dr. Peter L. Ilorris 2 furch 7,1968 e Welders were qualified under State of Michigan regula-tions, and all velds in the schedule 160 piping and the sold Ni. the piping specification change were radiographed. Analyses were perfomed by General Electric Company on - effectiveness of the supplementary core floodin6 system under two ecnditions: (1) Actuation after a rupture of the core spray line and t (2) Actuation after a break other than the core spray line where the core spray line remains intact. The. analyses were perfomed using the came methods as outlined and presented in Prcposed Changes 13 and 14 to the Big Rock Point Technical Specifications and supplement the results of those analyses. 4 1. In Condition No. 1, Fi6ure II shows the liquid -inventory versus tiuc. The analyses assume loss of feedvater at the 1 instant of the break and either the electric or dicsci fire pump operating. Curves are presented for the case of one control rod drive pump operating and for the case of no control rod drive pump operating. The enclosure spray and core spray lines were assumed to open, and the flov split among the three paths was calculated c= ploying the proper elevations and line resistances. The liquid inventory reaches levels.near the top of the core for both cases before flov to the reactor can begin at. approximtely 113 psig reactor pressure. Since the only loss is vapor through the broken core spray nozzle on the vessel (located above the core), the liquid level quickly increases. The analysis indicates the core is always cooled throughout the accident even though the top of the fuel might be exposed without control rod drive flow because of i .the frothing and steam that would exist. Therefore, the supple =entary core flooding system, as designed, provides adequate protection if the core cpray line is severed. 2. The analyses of Condition no. 2 show as a pctential. problem with the new supplementary core flooding system. Core spray flow would be diverted to the other two possibic flow paths, the core flood line and the enclosure spray. Figure III shows the response of the core spray system under various conditions. Core spray flov' decreases only slightly with the contaminant spray actuated, but the decrease in significant with the supplementary core flood line open, Flow resis-tances are the min concern here. Figure III shows flow through the supplementary flood line exceeding core spray flov at approximtely 107 psig reactor pressure and increases at a faster rate than core spray flow with decreasing reactor pressure. Core spray flov with the auxi-liary core flood line open vould provide only mrginsi cooling on the order of 0.01 gpm/ rod, as opposed to the current APED design value of 0.05gpm/ rod. Detection of a severance in the core spray line vould be difficult to detect durin6 a loss-of-coolant accident in the primry .. ~,.., _,,. - - ..,_.-~..c..-t n ,,3

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Dr.-Peter L. Morria 3 March 7,1968 cystem. Thus, a wron6 decision by the operator could occur, using the precent instrumentation in the control room. To provide adequate information to the operator for evaluation of the integrity of the core cpray line following a primary system rupture, we are inctalling a cmall instrument precoure cencing line between the MO 7061 valve and the check valve on the emergency core cooling line (cce print M-123,FHSR). Thic line vill read out in the control room via a newly connected transducer on the censing line. Reactor preccure Will produce a full scale cignG1 on the transducer when MO 7061 valve 1 is opened at. any given time to check and insure cystem integrity. A significant rupture of the core cooling line between i the check valve and vecnol vill result in a precoure cigual from the core cooling line cignificantly lower than reactor preccure. Thic loco of precoure, coincident with high precoure in the containment ophore, will require that the operator manually open the auxiliary core flood valvec. The above cyctem criteria has been checked by the General Office and the Big Rock Plant staff. Our plant operating procedures vill be baced on the above analysen and the appropriate perconnel vill be alerted to thic new procedure. In cu==ary, we believe that the cupplementary core flooding line vill provide the necessary backup in the event of a failure of the core spray line and that the possible adverce effects of this line can be eliminated by the planned precoure signal to the i control room. We vould also like to point ont that the above analysec are very conservative in that the new auxiliary station power cupply will be in cervice when we recume operation. Thic line provideo for the following: A. Simultaneous operation of both the electric and diecel fire pumps if necessary. B. Operation of either or both control rod drive pumps. C. Operation of either of the reactor feed i pumps. If the pu=po tripped coincident with the locc-of-coolant accident, one can readily be manually returned to service. Yours very truly, y ERC/lav R. L. Haucter Acciatant Electric Produ'etion CC: IEhornburg Superintendent - Nuclear , + - -m-- ---n

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