ML19211A610
| ML19211A610 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/05/1979 |
| From: | Souder J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Geschwindt J PENNSYLVANIA, COMMONWEALTH OF |
| References | |
| NUDOCS 7912200233 | |
| Download: ML19211A610 (7) | |
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UNITED STATES
- .g' p (g i y Yy c NUCLEAR REGULATORY COMMlSSION
/. p WASWNG TON. D. C. 2C555 e
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Novemoer 5,1979 Docket No. 50-289 m
- % @7 Mr. John Geschwindt
,,4 Government Publ' cations Section 2
M State Library of Pennsylvania 9-NgG Education Building O
gB Co=onwealth and Walnut Streets Harrisburg, PA 17126
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A
Dear Mr. Geschwindt:
u Enclosed are three binders cpntaining Babcock and Wilcox (B&W) generic corresoondence regarding the resolution Of issues. associated with all B&W designed 177 Fuel Assembly plants, including inree Mile Island, Unit 1 (TMI-1).
An index of this correspondence is also enclosed.
As you know, a hearing related to the Nuclear Regulatory Comission's (Cc-.i:sion's) Order of August 9,1979, concerning the restart of TMI-l is scheduled to begin shortly.
The subjects of the enclosed corresoondence serve as some of the bases uoon which the licensee (Metrocolitan Edison Company) has taken or will take actions directly related to the imediate and long-tenn recuirements of the Commission's Order.
Since many of these documents will be the subject of formal discovery in the uocoming croceedings, they will orove useful to hearing participants and the general cublic as well.
In the future, additional B&W generic documents and updated indices will be sent to you in order to kepn this file current.
A cocy of this letter and the Index of B&W Generic Corresoondence is being sent to the Service List for IMI-1.
A copy of that Service List is enclosed for your
'information.
Please feel free to contact me at any time concerning the Three Mile Island, Unit 1 collection and the availability of Comission documents.
Sincerely,
[ w., m/ r.
i NJ'9 d.
, Jona L. Souder, Chief f Local Public Document Room Branch Divisior of Rules and Reccrds Office c# Acministra-ion Er.:losu es:
1
.5&W Generic Corresponcence w/Index 2.
Service Lis:
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w 7 9122002 3 3
N, Y:.
g IllDEX OF Bf.W GLilERIC CORitESP0flDEllCE ASSOCIATED WITil Tile 1 A PLAflTS l'
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11 0.
DATE:
FR0ll:
T0:
SUBJECT:
[.(
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2
- (1979)~ ~ ~
(lilli)'
(flRC)
SlQ 1.
04/17 J. II. Taylor R. J. Mattson Revision to Operating Instructions in N) ig - A (111 Operation).
2.
04/20 Extract of B&W Conniunications (Change of PORV and liigh Pres Trip Setpoints),
3.
04/25 J.11. Taylor R. J. Mattson Sununary of 04/24 Hecting with staff (additional analyses reqaired),
4.
04/26 D.11. Roy R. J. Mattson Submittal of Detailed Analyses of B&W Operating Plant Respoi to Transients.
5.
04/28 J. II. Taylor
- 11. R. Denton Scope and Schedule for ICS Reliability Analysis and Schedule for Developing AFW Independent of ICS.
6.
05/03 J. II. Taylor R. J. Mattson Babcock and Wilcox Report BW-4689 " Pressurizer Reference Leg Effervescence Test"(Proprietary) Ltr. only sent to LPDR.
7.
05/04 J. II. Taylor D. F. Ross Coninents on "Sinnnary of Meeting with B&W Regarding flatural Circulation."
8.
05/05 J. II. Taylor R. J. Mattson
" Operating Pr ocedure Guidelines for Small Breaks."
9.
05/07 J.11. Taylor R. J. Mattson
" Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177 Fuel Assembly Plant" Volinnes I and 10.
05/08 J. II. Taylor R. J.liattson Revised Appendix 1 to Reference 9: "flatural Circulation in sp B&W Operating Plants (Revision 1)."
11.
05/10 J.11. Taylor T. M. flovak Background infonnation on RCP operr. tion in response to ilRC N
questions on Reference 9.
n LV J
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Page luo of Index 11 0,
DATE:
FROM:
10; SUDJECT:
12.
05/10 J. II. Taylor R. J. Mattson Provides reference PGlcrial and Supplement I to Appendix 2 t Reference 9:
" Steam Generator Tube lhermal Stress Evaluatic 13.
05/12 J.11. Taylor R. J. Mattson Provides to supplements to Reference 9:
Volume 1 Section 6.0-Supplement 1, "Small Break in the Pressurizer (PORV) with no Arw and Single failure of the E(
Voltane 1 Section 6.0-Supplement 2, "Small Break in the Pressurizer (PORV) with no AFW and Single Failure of the ECCS with Realistic Decay lleat."
14.
05/16 J. II. Taylor Z. R. Rosztoczy Revised " Operating Guidelines for Small Breaks", (incorporat staff comments).
15.
05/18 J. II. Taylor R. J. Ma ttson forwards " Report on Analysis Methods for RCS flatural Circulation," dated May 16, 1979.
16.
05/18 J. II. Taylor S. A. Varga Affhlavit to support praprietary request for Reference 6.
1/.
05/22.
J. II. Taylor
- 11. R. Denton independent AFW control System (Supplements Reference 5).
13.
05/24 J. II. Taylor R. J. Mattson Forwards Volume 1 Section 6.0-Supplement 3 to Reference 9 entitled, " Auxiliary feedwater Flow Required for 10CA."
~ 19.
05/25 J. II. Taylor T. M. Novak Analysis of sequential auxiliary feedwater flow to the O
steam generators for a loss of MFW using TRAP-2 ( Analysis V4 will be forwarded 6/15/79).
bJ 20.
05/25 R. Davis llMl Owners' Auxiliary Feedwater Testing (copy sent tollRC).
O v)
D
I' age lhree of Index 11 0.
DATE:
FROM:
T0:
SUBJECT:
Pl.
05/30 J. II. Taylor S. Israel Verification that AFW system will be adequate in the event of a total loss of main feedwater.
22.
06/13 J. II. Taylor R. J. Mattson Discussion of HRC Request for Additional Small Break Analys-Small Break LOCA with RCP trip at worst time.
23.
06/13 J.11. Taylor R. J. Mattson Conmitments Resulting from the THI-2 incident.
24.
06/13 J. II. Taylor D. F. Ross Response to Thennal Shock Concern.
25.
06/14 J.11. Taylor T. M. Novak Reactor Vessel Brittle Fracture During Small LOCA Events.
26.
06/15 J. II. Taylor R. L. Tedesco Notification that requested Semiscale Small Break Analysis will be delayed until October 1,1979.
27.
06/15 J.11. Taylor R. J. Ma ttson forwards analysis of sequential AFW flow to the OTSGs for a LOMFW transient.
2 11.
06/26 J.II. Taylor D. F.Ross forwards " Guidelines for Avoidance of Reactor Vessel Brittle fracture During Recovery from Small LOCA Events."
29.
07/03 J.11. Taylor D. F.Ross D&W response to the ACRS reconuendations related to T!11-2.
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Paye rour or.index HO.
DATE; FROM:
T0[;
SUBJECT:
30.
07/20 G. O. Geissler E. G. Case Forwards a representative lecter which was sent by B&W to all D&W Operating Plants on 07/20 concerning RCP trip in the event of ( n 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 NRC letter of 07/12 "Infonnation Request Reactor Vessel Brittle Fracture."
33.
08/16 J. II. Taylor D. F. Ross Submits scope and schedule for AFW System Reliability Analysis for B&W Plants.
34.
08/17 J. II. Taylor D. F. Ross forwards B&W Report RAW-1564 entitled, " Integrated Control System (ICS) Reliability Analysis."
35.
08/30 J. II. Taylor D. F. Ross Forwards a copy of the information which D&W transmitted to the B&W Owners' Group in response to IE Bulletin 79-05C.
36.
10/09 J. 11. Taylor R. P. Denise Analysis Prediction for Semiscale Test S-07-108.
37, 10/09 J. II. Taylor R. A. Capra Confirmation that no further action on D&W's part is requir for the non-LOCA overcooling transient analysis performed by Brookhaven flat. Labs.
38.
10/18 J.11. Taylor D. F. Ross Trip history of B&W Plants (comparison between B&W, W, and CE).
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