ML19220C083
| ML19220C083 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/29/1976 |
| From: | Israel S Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7904280189 | |
| Download: ML19220C083 (2) | |
Text
,
Docket Filc &
NRR Reading es RSB Reading Cocket No. 50-320 APR 2 9 m Richard C. DeYoung, Jr., Assistant Director for LWR;s, DPM THRU: Thomas M. Novak, Chief, Reactor Systems Branch, CSS THREE MILE ISLAND UNIT 2 AMENCMENT 40 REVIEW Plant Name: Three Mile Island, Unit 2
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Docket No.: 50-320 Milestene No.: 24-21 Licensing Stage: OL Responsible Branch & Project Leader: LWR-2, H. Silver Technical Review Branch Involved: Reactor Systems Bracch Cescription of Review: Review of FSAR Amendment 40 (4-20-76)
Requested Completion Date: November 19, 1976 Review Status: Awaiting Infont.ation The Reactor Systems Branch has reviewed sections of a oreliminary Amend-ment 40 to the FSAR. We find that the issues addressed do not satisfy the openfitems in the draft SER. The attached com.cnts and cuestions are intended to aid the appitcant in properly addressing the issues.
Original signed by:
S. Israel, Section Leader Reactor Systems Branch Division of Systens Safety Enclosure Questions & Cor.nents cc:
S. Harauer R. Heineman D. Ross h
r Kniel H. Silver T. Novak
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21 2-1 212.0 REACTOR SYSTE:'S E'A'Pu 21.35 The aranded ressense to this questien dcas not demen tra:c (6.3.2) adecuate ctre ccciing fcr ei+hcr the srcrt or 'ang tera followine a core ficoding line Dreak coincident with loss of the dicsal pcwering the uref fected train.
A.
In item 2 of the response, Iccal cperatcr action is required to ccan crossover ir.e valves and isolation valve; to achiace ficw tl.rc.4h the unbroken LPI lir.e to the reactor.
In the a'ssn:2 cf pcxer to a throttle c
valva, describe hcx the ficw is balanced between the broken and unbroken lines. Provice a breakdcwn of the time involved in:
a) Making the determinaticn that a man will have to be dispatched to make the ranual valve actions, include tita for ettempts to restart ths diesel.
b) Provide realistic and conservative times for a man to physically position the valves.
c) Describe thz time avail:ble assuming the LPI pump is left at runout ficw.
Icantify the time raargin.
B.
It i: a st:ff c:n:Grn relati ca to this accident than the FPI pump will be lost due to inadaquate riPSH uten switch-over from the injection te r3 circulation modes.
The applicant should provice the ?:PSH available to the FF:
pumps folicwing switchover assuming (1) 1500 GPM har been provided to eacn line, and (2) that 3,C:0 GPP is creviced to the broken line. He shculd assess wnacher the lip' pumps will be lost in either case.
If credit is ts%er for thrcttling fica with tne iscletien vcive in c :c 1, describe how the b:;ak locaticn is determined by thc c:arator.
C.
The ECCS evaluaticn has not ceen ccmpleted by the st=f' relative to iMI-2.
Provice a PTss balance curing Sne ccre ficoding line break to verify the water level in the :sre.
21.51 Thi: section references a letter frca the staff cermittina (7.8.3) cceration of the Ba',! reactors without a penalt" for ir.tcr5als vert valve leakage. The section :tates that the valves ill ';
c installed withcut leakage detecti;n therroccuples.
~ 0 2;plicac.
must describe the recuirerents for internals vant v5ive tastir t at each.efueling noted in the le:ter.
The testing requirs "c:
should be delineated in the ap;rocriata Technical Specificati'-
and refererced in Section 7.3.3.
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