ML19254F412
| ML19254F412 | |
| Person / Time | |
|---|---|
| Site: | Crane, Rancho Seco  |
| Issue date: | 10/29/1979 |
| From: | Capra R NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| To: | Souder J NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| NUDOCS 7911090250 | |
| Download: ML19254F412 (5) | |
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Cc:cter 29, 1979
.,ocx, e t,. cs: au-tos & au-a-,c-v MEMORANCUM FOR:
J. L. Scuder, Chief, Local ?ublic ::c men: :: 5cancn, Division of Rules and Records FROM:
R. A. Capra, B&W Project Manager, Projec: zar. gemen; 3rou:,
Bulletins and Orders Task Force S L,B u, u-.
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LOCAL PUBLIC CCCUMEtiT ROCMS FOR RA..:HO SECO i.: 7"I As you are aware, hearings are pencing for the Rancn: Sec; :. :'._r.' 3enera:in; Station and the Three Mile Island iluclear Staticn, uni: 1.
-nese'nearings are related to the Comission Orders issued on May 7 anc Augas: 9, 1979, respectively.
Since the accident at T'1I-2, many documents have been receive: cy the i:RC directly from Babcock and 'iilecx regarding the resci :icn of issues associa:ec with all B&W designed 177 Fuel Assembly plants. This cesign incluces Rancno Seco and TMI-l.
The subjects of the correspondence are the bases ;;cn '.snich.nese li:ensees have taken or will take actions directly relatec :c :n2 'cre:'a:e a c icng-te m requirements of the Ccmission Orders. Mcwever, tre.::Rs for :cesa facili:ies were not includec on distributica.
I request that you establish a separate file of :nese dccuments i
- ne.?:?s for Rancho Seco and TMI.
I will assure that ycu recei.'e :nesa :/:es of :ccu. cents in the future in a more timely fashion. This file :.ii'. be useful c :ne pu;iic and the staff, since many of these documents will be :he su jec: of formai discovery in both proceedings. is an index of the correspondence incluued in :nis ac nage.
I will ask OELD to send a copy of this index to the interver. ors wi:n an explanation that this material may now be founc in :ne L.::Rs.
If you need additional information, please contac: te a X-27725.
~~R. O. %7_._ /
R. A. Caora, 3iu.:r:je:: ar.ager
Enclosures:
Prcject ana emen; 3r:L:
1-Index of B&W Generic Corres.
Bulletins anc Or:ers Tass ::r:e 2-Copies of items listed on Encl. I
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1 7 911090 a TO H
lilDEX OF B&W GErlERIC CORRESP0flDENCE ASSOCIATED WITil Tile 177FA PLAtlTS N
40.
DATE:
FROM:
T0:
SUBJECT:
(1979)~
(If&UT (NRC) 1.
04/17 J. II. Taylor R. J. Mattson Revision to Operating Instructions in IE Bulletin 79-05A (llPI Operation).
2.
04/20 Extract of B&W Conmunications (Change of PORV and liigh Press.
Trip Setpoints),
3.
04/25 J. II. Taylor R. J. Mattson Sunmary of 04/24 Meeting with staff (additional analyses required),
4.
04/26 D. 11. Roy R. J. Mattson Submittal of Detailed Analyses of B&W Operating Plant Response to Transients.
5.
04/28 J. fl. Taylor
- 11. R. Denton Scope and Schedule for ICS Reliability Analysis and Schedule for Daveloping AFW Independent of ICS.
6.
05/03 J. 11. Taylor R. J. Mattson Babcock and Wilcox' Report BU-4689 " Pressurizer Reference Leg Effervescence Test"(Proprietary) Ltr.only sent to LPDR.
7.
05/04 J. II. Taylor D. F. Ross Coinnents on "Sunmary of Meeting with B&W Regardirm f.ati:ral Circulation."
8.
05/05 J. II. Taylor R. J. Mattson
" Operating Procedure Guidelines for Sinall Breaks."
9.
05/07 J. II. Taylor R. J. Ma ttson
" Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177 fuel Assembly Plant" Volumes I and II.
O.
05/08 J. II. Taylor R. J. Mattson Revised Appendix 1 to Reference 9: "flatural Circulation in B&ll Operating Plants (Revision 1)."
1.
05/10 J. II. Taylor T. M. Novak llackground infonnation on RCP operation in response to flRC questions on Reference 9.
2.
05/10 J.11. laylor R. J. Mattson Provides reference material and Supplement I to Appendix 2 to Reference 9:
" Steam Generator Tube lhennal Stress tvaluation."
3.M' 05/12 J.11. Taylor R. J. Mattson Provides to supplements to Reference 9:
CD Volume 1 Section 6.0-Supplement 1, "Small Break in the Pressurizer (P0HV) with no Afu and Single failure of the ECCS."
Volume 1 Section 6.0-Supplement 2, "Small Break in the
[
Pressurizer (PORV) with no Aftl and Single failure of the ECCS with Realistic Decay lleat."
m
Page Two of Index fl0.
DALE:
FROM:
T0;
SUBJECT:
14.
05/16 J.11. Taylor Z. R. Rosztoczy Revised " Operating Guidelines for Small Breaks", (incorporating staff conanents).
15.
05/18 J.11. Taylor R. J. Mattson forwards " Report on Analysis Methods for RCS tlatural Circulation," dated May 16, 1979.
16.
05/18 J. II. Taylor S. A. Varga Affidavit to support proprietary request. for Reference 6.
17.
05/22 J. II. Taylor
- 11. R. Denton Independent AFW Control System (Supplements Reference 5).
i 18.
05/24 J. II. Taylor R. J. Hattson Forwards Volume 1 Section 6.0-Supplement 3 to Reference 9 entitled, Auxiliary Feedwater Flow Required for LOCA."
19.
05/25 J.11. Taylor T. M. flovak Analysis of sequential auxiliary feedwater flow to the steam generators for a loss of MFW using 1 RAP-2 (Analysis will be forwarded 6/15/79).
20.
05/25 R. Davis D&ll Owners' Auxiliary Feedwater Testing (copy sent to NRC).
21.
05/30 J. II. Taylor S. Israel Verification that AfW system will be adequate in the event of a total loss of main feu! water.
22.
06/08 J. II. Taylor R. J. Mattson Discussion of NRC Request for Additional Small Dreak Analysis:
Small Break LOCA with I CP trip at worst time.
23.
06/13 J. II. Taylor R. J. Mattson Conmitments Resulting from the 1MI-2 incident.
24.
06/13 J. II. Taylor D. F. Ross Response to Thennal Shock Concern.
25.
06/14 J. II. Taylor T. M. flovak Reactor Vessel Brittle Fracture During Small 10CA Lvents.
26.
06/15 J. II. Taylor R. l.. Tedesco flotificat. ion that. requeste<l Semiscale Small lireak Analysis
~
will be delayed until October 1,1979.
u C
27.
06/15 J. II. Taylor R. J. Ma ttson Forwards analysis of sequent.ial AfW flow to t he OISGs for a LOMfW transient.
28.
06/26 d.11. laylor D. F.Ross forwards " Guidelines for Avoidance of Reac. tor Vessel Brittle y
Fracture During Recovery from Small LOCA Events."
2".
07/03 J. II. Taylor D. F.Ross B&ll response to tne ACRS reconmendations relate <l to Ili!-2.
Paue Three of Index 4
flu.
DATE:
FROM:
T0:
SUBJECT:
30.
07/20 G. O. Geissler E. G. Case Forwards a representative letter which was sent by B&W to all B&W Operating Plants on 07/20 concerning RCP trip in the event of an ESFAS actuation.
31.
08/01 J. ii. Taylor R. J. Mattson AFW Flow Rate Sensitivity Study.
32.
08/03 J. II. Taylor D. F. Ross Response concerning flRC letter of 07/12 "Information Request Reactor Vessel Brittle Fracture."
33.
08/16 J.11. Taylor D. F. Ross Submits scope and schedule for AFLl System Reliability Analysis for B&W Plants.
34.
08/17 J.11. Taylor D. F. Ross Forwards B&W Report BAW-1564 entitled, " Integrated Control System (ICS) Reliability Analysis."
3a.
08/30 J.11. Taylor D. F. Ross Forwards a copy of the information which B&W transsitit ted to the B&W Owners' Group in response to IE Bulletin 79-05C.
36.
10/09 J. II. Taylor R. P. Denise Analysis Prediction for Semiscale Test S-07-108.
37.
10/09 J.11. Taylor R. A. Capra Confirmation that no further action on B&W's part is required for the non-LOCA overcooling transient analysis perfonned by Brookhaven Nat. Labs.
38.
10/18 J. II. Taylor D. F. Ross Trip history of B&W Plasits (coinparison between B&ll, W, and CE).
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