ML19211A614

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Forwards Index of B&W Generic Correspondence Re Resolution of Issues Associated w/177 Fuel Assembly Plants
ML19211A614
Person / Time
Site: Rancho Seco
Issue date: 11/05/1979
From: Souder J
NRC OFFICE OF ADMINISTRATION (ADM)
To: Harvey D, Holmes G
AFFILIATION NOT ASSIGNED
References
NUDOCS 7912200243
Download: ML19211A614 (7)
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Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D. C. 20555 f

ng November 5,1979 conng UD.v t, g i,n Ee Docket No. 50-312 3

Y U

N%3% -

4" Mrs. Dorothy Harvey

[(O f.'.- [!

@h ATTN: Gabriel Holmes 4 /@M,1 F

Business and Municipal Department Sacramento City-County Library p

828.I Street

'o s

Sacramento, CA 95814

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Dear Mrs. Harvey:

Enclosed are three b:.ders containing Babcock and Wilcox (B&W) generic correspondence regarding the resolution of issues associated with all B&W designed 177 Fuel Assembly plants, including Rancho Seco.

An index of this correspondence is also enclosed.

As you know, a hearing related to the Nuclear Regulatory Commission's

(_ Commission's) Order of May 7,1979 confirming the snutdown of Rancno Seco is scheduled to begin shortly.

The subjects of the enclosed corresoondence serve as some of the bases upon which the licensee (Sacramento Municipal Utility District) has taken or will take actions directly related to the immediate and long-term requirements of the Commissien's Order.

Since many of these documents will be the subject of femal ciscovery in the upcoming oroceedings, they will prove useful to hearing particioants and the general oublic as well.

In the future, additional B&W generic documents and uodated indices will be sent to you in order to keep this fiie current.

. A copy of this letter and the Index of B&W Generic Ccrrescondence is being sent to the Service List for Rancho Seco.

A cooy of that Service List is enclosed for your information.

Please feel. free to contact me at any time concerning the Rancho Seco LPDR collection and the availability of Commission documents.

Sincerely, d

6{1 ona L. Souder, Chief 1/ocal Public Documen: Room Branch ivision of Rules and Records Office of Acministration

Enclosures:

1.

B&W Generic Correscondence w/Index 1633 253 2.

Service List 7 912200 2 4 3

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q INDEX OF B&W GEllERIC CORRESP0flDEllCE ASSOCIATED WIIll Tile 17)[A PL fiYS (f

8 b

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11 0.

DATE:

FROII:

TO:

SUBJECT:

0

- (1979)

(BMI)'

(ilRC) 1.

04/17 J.11. Taylor R. J. Mattson Revision to Operating Instructions in IE Bulletin 79-05A (Il Opera tion).

2.

04/20 Extract of B&W Cormiunications (Change of PORV and liigh Pres Trip Setpoints),

3.

04/25 J. II. Taylor R. J. Mattson Suninary of 04/24 fleeting with staff (additional analyses required),

4.

04/26 D. II. Roy R. J. itattson Submittal of Detailed Analyses of B&W Operating Plant Respo to Transients.

5.

04/28 J. II. Taylor ll. R. Denton Scope and Schedule for ICS Reliability Analysis and Schedul for Developing AfW Independent of ICS.

6.

05/03

d. II. Taylor R. J. Mattson Babcock and Wilcox Report BW-4689 " Pressurizer Reference leg Effervescence Test"(Proprietary) Ltr. only sent to LPDR.

/.

05/04 J. II. Taylor D. F. Ross Coimients on "Sunmary of Meeting with B&W Itegarding flatural Circulation."

8.

05/05 J.11. Taylor R. J. Mattson

" Operating Procedure Guidelines for Small Breats."

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

& 10.

05/08 J. II. Taylor R. J. Mattson Revised Appendix 1 to Reference 9:

"flatural Circulation in U

B&W Operating Plants (Revision 1)."

u y 11.

05/10 J. II. Taylor T. M. flova k Background infonnation on RCP operation in response to ilRC w

questions on Reference 9.

Page Two of Index t10.

DAlf :

IROM:

T0; SlH1 JECT:

12.

05/10 J.11. Taylor R. J. Mattson Provides reference material and Supplement I to Appendix 2 t Reference 9:

" Steam Generator Tube Thermal Stress Evaluatio 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 EC Volume 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 ccmments).

15.

05/18 J. II. Taylor R. J. Mattson forwards " Report on Analysis ficthods for RCS flatural Circulation," 3ated May 16, 1979.

16.

05/18 J. II. Taylor S. A. Varga Affidavit to support proprietary request for Reference 6.

17.

05/22 J.11. Taylor ll. R. Denton Independent AFW Control System (Supplements Reference 5).

18.

05/24 J. II. Taylor R. J. Mattson forwards Volume 1 Section 6.0-Supplement 3 to Reference 9 encilled, " Auxiliary Feedwater Flow Required for i.0CA."

Os u l9.

05/25 J.11. Taylor T. M. flovak Analysis of sequential auxiliary feedwater flow to the u

steam generators for a loss of MFW using TRAP-2 ( Analysis will be forwarded 6/15/79).

ru Q 20.

05/25 R. Davis DAW Owners' Auxtllary Feedwater Testing (copy sent toilRC).

w

Page Three of Index 11 0.

CUE:

FROM:

T0:

StlBJECT:

21.

05/30 J. II. Taylor S. Israel Verification that Afu system will be adequate in the event of a total loss of main feedwater.

22.

06/08 J. II. Taylor R. J. Mattson Discussion of HRC Request for Additional Small Break Analysi Small Break LOCA with RCP trip at worst time.

23.

Ot/13 J. II. 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. II. Taylor T. M. Novak Reactor Vessel Brittle fracture During Small LOCA Events.

26.

06/15 J.11. Taylor R. L. Tedesco Notification that requested Semiscale Small Break Analysis will be delayed until October 1,1979.

27.

06/15 J. II. Taylor R. J. Mattson Forwards analysis of sequential AfW flow to the OTSGs for a LOMfW transient.

?H.

06/26 J. II. Taylor

1). f.Ross forwards " Guidelines for Avoidance of Reactor Ve,sel lirittlt fracture During Recovery from Small LOCA f. vents."

29.

07/03 J. II. Taylor D. F.Ross IMW response to the ACRS recuanendations related to Illi-2.

Ch uu L.IT Ch

l' age rone of.Index tl0.

DME:

FROM:

T0;

SUBJECT:

30.

07/20 G. O. Geissler E. G. Case Forwards a representative letter which was sent by D&W to all B&W Operating Plants on 07/20 concerning RCP trip in the event of an ESFAS actuatien.

31.

08/01 J. II. Taylor R. J. Mattson AFW Flow Rate Sensitivity Study.

32.

08/03 J. II. Taylor D. F. Ross llesponse concerning flRC letter of 07/12 "Infonnation Request Reactor Vessel Brittle Fracture."

33.

08/16 J.11. Taylor D. F. Ross Submits scope and schedule for AFW System Reliability Analysis for il&W Plants.

34.

08/17 J. II. Taylor D. F. Ross Forwards B&W Report DAW-1564 entitled, " Integrated Control System (ICS) Reliability Analysis."

35.

08/30 J. II. Taylor D. F. Ross Forwards a copy of the information which IIAt3 Iransmitted to the BAW Owners' Group in response to if linilclin 79-05C.

tf..

10/09 J. II. Taylor it. P. Denise Analysis prediction for Semiscale Test s-0/-1011.

t /.

10/09 J. II. Taylor

11. A. Capra ConfIrmaL ton ti aL no forther acLfon on itAW*s part is regnire for the non-LOCA overcooling transient analysis perlonned by Brookhaven flat. Labs.

.t:1 10/18 J. II. Taylor D. F. Ross Trip history of B&W Plants (comparison between 11&W, W, g

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