ML19322C376
| ML19322C376 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, Crane |
| Issue date: | 06/06/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001160910 | |
| Download: ML19322C376 (3) | |
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/,e raucLEAR REGUL ATORY COT.P.ussIOi1
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, i.,. y'2Q,., i S W WW4G 7 0*J. C. C. 20555 June 6,1978
...y k cuo seco t1Af2.CW 90, RT MEMORAf;0UM FOR:
Brian Grimes, Assistant Director for Engineering &
Projects,00R E
FR0il:
' Robert H. Reid, Chief, Operating Recctors Branch !4, D0R
SUBJECT:
I.EADOTRA!jsFER ON B≪INSTRUM5HTATION)
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Per your request same subject, dated May 17, 1978, the following lead engineer assignments have been designated by the respective Branch Chiefs:
y Plant Systems Branch:
M. Chiramal Reactor Safety Branch:
R. Lobel ggs go R.
G. Zwetzig A definition of th'e various tasks is given in the attachment.
The target completion schedule and estimated personpower requirements are as follows:
TASK TARGET COMPLETION DATE EST. EFFORT (PER50!!-MEEKS) 1 07/31/78 1.7 2alb 09/18[l8 0.5 2c 12/18/78 2.1 3a 07/31/78 4.1 3b 09/18/78
- 0. 8' 4a(Review)*
10/09/78 2.6 (Implementation) 03/26/79 2.8 4b 07/31/79 5.4 TOTAL 20.0 "Corsietica of Iten 2 of V. Steilo's letter of "/7/7?. cis:'r.c lEC ty cc
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lpil R 9 9)d,wWatI)ghbun.a I
h 8001100 9/O p
Me;ro for B. Grirr.es
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The related task on revised Technical.Specificat. ions for reactor heatup/cooldown rates is being pursued independently by R. Klecker and J. !kGough.
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Robert W. Reid, Chief Operating Reactors Branch !4 Division of Operating Reac, tors Attacliment:
Task Definiti6ns cc w/ attachment:
V. Stello R. Baer P. Check W. Butler G. Lainas D. Tondi M. Chiramal G. Zwetzig O. Eisenhut R. Klecker J. McGough ff)] h.h \\
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t TASK DEFI.'!ITIONS_
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Efforj non:nuc1 ea rfinstruinentat i oin ((n#1 lia t SR
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PDstermir!eJfichangescare neededy,,nldEYi,g._f; power
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. Task l
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o;to re d6c e p roba bi f i~(9~5 f ~ 16s s^iff' c o n t ro l i n fo riiR iiinT
. Task 2 If conclusion of Task 1 is affirmative Determine which, if any, B&'d reactors have power supply a.
designs which are susceptive to same failure mode as Rancho Seco design, and Request Rancho Seco and facilities identified in Task 2a b.
to' propose an impr.oved design, and submit a safety evaluation showing the acceptability of the improved' design.
Determine the acceptability of the proposed improved designs c.
and advise affected licensees accordingly.
Task 3a. g_Revies.autoinatic Linitia' tion r of _auxil iarytfeidwater-fl,o,w, e._,-.---.y,,_,__
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Gbyma _Sa fety J ea tu re sjet u a tioii!S ijnia C( S FA S )' Tid ~de thEiii n e yhether;thisMdaturetshould be retained,by Rancho Seco.
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b.
If it is concluded that this feature sh'opld be deleted, take appropriate licensing action for Rancho Seco and r
p-other B&W facilities with a similar design, if any.
[R5VieTBMCddsi giiEdTpl snts EfoF6thieE jenerIieTddii[ENiituh Task 4a.
twhsfe3nticipa,tedsfa116reshrliiittiat ngMVedtsI6oUld cause significant cooldown transients, and take licensing action as appropriate.
b.
Same as 4a for Westinghouse and CE plants.
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