ML19322D169
| ML19322D169 | |
| 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 |
| Shared Package | |
| ML19322D168 | List: |
| References | |
| TASK-2.K.2.13, TASK-TM TAC-45198, NUDOCS 8002100005 | |
| Download: ML19322D169 (3) | |
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.J UNITED $TATES
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pluCLEAR REGULATORY COMMi$slON 5::: - l 0-WASHINGTON. C. C. 20555
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- E;EE MEMORANDUM FOR: Brian Grimes, As.sistant Director for Engineering &
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Robert W. Reid, Chief, Operating Re&ctors Branch !4, DOR L.....i.
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SUBJECT:
LEAD TRANSFEP. ON B&W INSTRUMENTATION
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Per your request same subject, dated May 17, 1978, the following lead
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engineer assignments have been designated by the respective Branch I.7 Chiefs:
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Plant Systems Branch:
M. Chiramal t ;. _
Reactor Safety Branch:
R. Lobel ORBi4 (Project Lead):
G. Zwetzig u;; ;;-
l A definition of th's various tasks is given in the attachment.
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The target completion schedule and estimated personpower requirements F
are as follows:
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TASK TARGET COMPLETION DATE EST. EFFORT (PERSOH-WEEKS)
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07/31/78 1.7
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2c 12/18/78 2.1 55 i
3a 07/31/78 4.1,
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10/09/78 2.6
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l (Implementation) 03/26/79 2.8
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4b 07/31/79 5.4 EE..:.
l TOTAL 20.0
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- Corpiecion of Ite.- 2 of V. Stello's letter of 4/7/75. ru-i..; lE iy cc pletion rea::est.
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The.related task on revised Technical. Specifications for reactor f!L.
heatup/cooldown rates is being pursued independant1y by R. Klecker
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and J. McGough.
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Robert W. Reid, Chief
?.T Operating Reactor: Branch f4 0.2 Divisio'n of Operating Reactors ig.,j
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Attachment:
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, Task Definiti6ns
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cc w/ attachment:
V. Stello R. Baer e ~..
- P. Check W. Butler G. Lainas
' D. Tondi M. Chiramal G. Zwetzig
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D. Eisenhut R. Klecker Z..~.
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TASK DEFIF.ITIONS py'**'
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~. Task 1 Determine if changes are needed in design of power supply for non-nuclear instrumentation (!!NI) at Rancho Seco to E.3 reduce probability of loss of control information.
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. Task 2 If conclusion of Task 1 is affirmative a.
Deterinine which, if any, B&W reactors have power supl;1y
,p designs which are susceptive to same failure mode as gy.
di9 Rancho Seco design, and T....
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Request Rancho Seco and facilities identified in Task 2a i
to propose an impr.oved design, and submit a safety f.T" evaluation showing the acceptability of the improved
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design.
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o Determine the acceptability of the proposed improved designs c.
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and advise affected licensees accordingly.
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Task 3a.
Review. automatic initiation of auxiliary feedwater flow t
b by a Safety Features Actuation Signal (SFAS) and determine F
whether this feature should be retained by Rancho Seco.
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if it is concluded that this feature sh'op1d be deleted,
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(take appropriate licensing action forftancho Seco and J
other B&W facilities with a simfTar design, if any.
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Task 4a.
Review B&W designed plants for other generic desig'n featuhes W.5 where anticipated failures or initiating events ~could cause is..%
significant cooldown transients, and take licensing action
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Same 'as 4a for Westinghouse and CE plants.
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