ML19289G244

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Responds to 770401 Request for Info Re Investigations of Allegations of Withholding of Steam Generator Info. Technical Staff Responses Encl
ML19289G244
Person / Time
Site: Surry, North Anna, 05000434, 05000435  Dominion icon.png
Issue date: 05/05/1977
From: Shapar H
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Taft P
JUSTICE, DEPT. OF
Shared Package
ML19289G243 List:
References
FOIA-79-214 NUDOCS 7908080692
Download: ML19289G244 (12)
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Text

{{#Wiki_filter:. .c ,s ..u..,..=_. WASHWGTON. D. C. 20555 (, ' ' ) ) %..v / MAY 5 1977 Peter R. Taft, Esq. Assistant Attorney General Land and Natural Resources Division United States Department of Justice Washington, 0.C. 20530 Ref: ATG:PMK (90-5-1-7-220)

Dear Mr. Taft:

In accordance with your request of April 1, 1977 regarding your continued investigation of allegations concerning the North Anna and Surry installations, there are enclosed answers to your 13 questions which have been prepared by cur technical staff. While the answer given to question 13 was no, we would, of course, wish to re-examine this matter in the light of any new information your investigation may disclose. Please feel free to contact me if you need additional information ~ or assistance in this matter. Sincerely, s //$ f W Howard K. Shapar Executive Legal Director Enclosure": See page 2 2084 003 79 08080cSR ^ .,.;,Y.'<.*:.hi,'.ij e ^ ~ ~ u.- .gg y :;;t, ;t 4:h,'.i ;,.. ~~ * ] ~, d,,,,.- ,;.'.5 M .. '(*;,. WQ l',f,.. ', g*;g*.~.,, u'.:, J: ~-:- l_ e , c - ~,,- - -.g g y g : g -c d q.

e' s i Peter R. Taft, Esq. ..- 2 May 5, 1977 ENCLOSURES 1. RESPONSES TO QUESTIONS 1 THROUGli 13 Ift THE DEPARTMEtiT OF JUSTICE LETTER DATED APRIL 1, 1977 CONCERN!f;G THE f;0RTH Afu!A POWER STATION, UNITS 1 aid 2 STE,V1 GEf!ERATOR SUPPORTS 2. LETTER DATED APRIL 5, 1977 TO VEPC0 FROM DUDLEY TH0$PSON -ACTIf:G DIRECTOR, DIVISI0il 0F FIELD OPERATIO!!S, OFFICE OF liiSPECTI0ft & EllFURCEME!iT 3. CORRECTED COPY OF TRAllSCRIPT OF APRIL 13, 1976 DISCUSSIO:: BETWEEN NRC AND c VEPC0 - STEAM GENERATOR LOWER AND REACTOR C00LAflT PUMP SUPPORTS 4.

SUMMARY

OF MEETIf;3 HELD ON JULY 21, 1976 CONCERilli!G STEAM GENERATOR AfiD REACTOR C00LAf1T PU;iP SUPPORT STRUCTURES 5. TRANSCRIPT - ADVISORY CCMMITTEE O!! REACTOR SAFEGUARDS SUCCOMMITTEE MEETir:G CF JUl.Y 7,1976 CONCERNING fiORTH Ai:MA POWER STATIGH, VilITS 1 AND 2 STE/41 GEllERATOR SUPPORTS 6. TRANSCRIPT - ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SUBCOMMITTEE MEETIf;G OF OCTOBER 13,'1976 CONCERN!f G fiORTil ANNA POWER STATI0fi, UtilTS 1 AND 2 STEAM GEli[RATOR SUPPORTS 7. SUPPLEMENT f!0. 3 TO THE fl0RTil ANNA POWER S1 ATION, UlllTS 1 AND 2 SAFETY I EVALUATICH REPORT 8. SUPPLEME!!T !;0. 6 TO Tile fiORTH AliflA POWER STATION, UNITS 1 AfiD 2 SAFETY EVALUATION REPORT 9. STEAM GEliERATOR AfiD REACTOR COOLANT PUMP SUPPORTS 10. LETTER DATED fiOVEMCER 19, 1976 TO MR. BERNARD RUSCiiE, DIRECTOR, CFFICE OF fiUCLEAR REACTOR REGULATION FRCM SAM C. CROWN, JR., VICE PRESIDE:li, PC'.lER SECTION, EliGINEERII;G AND CONSNUCTION, VIRGINIA ELECTRIC AND POWER COMPANY 21384 004 0

~ EflCLOSURf_l, RESP 0ilSES TO 00ESTIO:lS 1 THROUGli 12 Itt Tile DEPARTMCIT OF JUSTICE LETTER DATED APRIL 1,1977 C0tiCERfilf!G THE i;0RTli Ai;i:A PO'< ER STATIO 1, U::ITS 1 A!!D STEA!1 GEllERATOR SUPPORTS Question 1 The document discusses the brittle-fracture properties of the steam generatt supports at the florth Anna site. In particular, i t suggests that the structures are subject to brittle-fracture failure and collapse at the original design operating temperature. Is this conclusion reasonable and is the analysis sound?

Response

Although the report discusses the subject of brittle-fracture, it dcas not conclude that steam generator supports at florth Anna are subject to collapse at the design operating temperature. i The report objective was to calculate flaw sizes in these structures which could propagate as cracks under the most severe design conditions i.e., very low probability accidents. The analytical methods which were used are sound. However, extremely conservative assumptions were made regarding the material toughness, strain rate, loading conditions and flaw shapes. The report describes this apprcach as choosing for every variable "that l value which would minimize the critical flaw size." This approacn is use-full for scoping purposes but the likelihood of all or many of the factors being at the most adverse condition at a given point in time is so remote as to render such an analysis unsuitable for usual engineering design purposes. i To the vast majority of practicing structural engineers the import of ,' such an analysis is to demonstrate that particular attention should be paid to the relief of residual stresses and to other fabrication and ' inspection procedures to ensure that as many of the factors as possible - are well removed from the levels assumed in the analysis. This step ,' in conjunction with a total support system evaluation would taen provide the basis for detenaining acceptability of the design. 2084 005 0

l i i ..2. Question 2 is there any reasonable basis in that document for concluding that the support structures are acceptable as designed? If so, what is that basis? Response _ The document (CC-81) does not evaluate acceptability of the l' orth Anna _ component supports for the intended service nor does it state any conclusions to that effect. Additional information must be available p _before reasonable conclusions can be made.xo21c.e_tI11.ag J nL ag eptac111ty of th Such informat.icn would include stress analyses 'of Tn,e support structurj;,..ese structures and details of the repair procedures and n examinations which were performed during the course of the repair. [ basis for concluding that brittle-fracture in the as-repaired supportna / i structures would be unlikely at the design operating temperature. This ( conclusion does not necessarily preclude the possibility, although very ) Analyses perfomed by Stone and Webster and verified by indepe / staff analyses have shown substantial structural redundancy in these k structures..Thus in the event that brittle-fracture should occur in one N.or more major members, despite all the measures taken to prevent it, failut /to the extent that would affect the overall function of the support or / safety of the plant would not occur. Increasing the operating temperature (ofpartso,fthestructuresfurtherincreasesthemarginofsafety. Question 2 Do the analyses and conclusions in the document raise ~a safety-related matter that the Commission feels should have been reported pursuant to 10 CFR 50.55?

Response

t I n a letter dated April 5,1977 to VEPC0 (Enclosure 2), the NRC staff I stated that a review of the document (DC-81) has resulted in the conclusic s that report DC-81 did not contain information that significantly af#ccted d \\ the findings by the staff and was not a matter which racuired recortinq __ !under10CFR50.55e. 1 Question 4 Was th: subject document submitted to the Con:nission at any time prior to Sun's submission in 1976? 2084 006 0

I-i ' ' C 3 '-

Response

The subject document was not submitted to the Coimtission at any time prior ~ to Sun's submission in 1976. Question 5 Did VEPC0, Stone and Webster, or any other contractor or consultant inform the Commission of the risk of brit.tle fracture prior to Sun's submission? Response _ !!either VEPCO, Stone and Webster nor any other contractor or consultant informed the Comnission of the risk of brittle fracture crior to Sun's submission. Ouestion 6 If so, who gave the information, on what date(s), and in what form was it presented to the Conmission? ' Response ci flot Applicable. 0uestion 7 Please forward copies to us of any cor.a.;unications to the Comission that are described in the previous question.

Response

tiot applicable. 2084 007 o

,,--4.,--_. ~ ~~ Question 8 We understand that VEPC0 made a presentation to the Commission regarding the brittic-fracture properties of the North Anna supports. Please forward to us a copy of any materitis furnished the Commission as a result of that presentation.

Response

Several presentations were made by VEPC0 to the NRC staff and the Advisory Committee on Reactor Safeguards. The infonaation presented by VEPC0 is presented in (1) " Corrected Copy of Transcript of April 13, 1976 Discussicn Between MRC and VEPC0 - Steam Cenerator Lower and Reactor Coolant Pump Supports" (Enclosure 3), (2) " Summary of Meeting Held on July 21, 1976 Concerning Steam Generator and Reactor Coolant Pump Support Structures" (Enclosure 4), (3) " Transcript - Advisory Committee on Reactor Safeguards Subcommittee Meeting of July 7, 1976 Concerning North Anna Po,.er Station Units 1 and 2 Steam Generator Supports" (Enclosure 5), and (4) " Transcript - Advisory Committee on Reactor Safeguards Subccmmittee meeting of October 13, 1976 Concerning North Anna Power Station, 'Jnits 1 and 2 Steam Generator Supports" (Enclosure 6). Question 9 We also understand that substantial design modifications have been developed for North Anna as a result of the brittle-fracture question. Please describe tl'ose modifications in detail and furnisn copies of any reports describing or evaluating them that were prepared by the Commission or by VEPC0 or any cf its centractors or consultants.

Response

/ Substantial m_odi,ficatio.ns to the original. design _of..the steam generator sjuppo'tswerenot_rqquired. The desired effect of increasing'the' te'mpera ture ~ r 1 l of the memb.es in question was accomplished by the addition of an inculation " M around the support structures and the provision of electric space l heaters within the " tent". Necessary instrumentation is provided to c:anitor the structural member tenperature. Administrative controls in the Technical Specifications identify a minimum structure member temperature which must be attained before the reactor primary system can be pressurized above a specified ;imit. 2084 008 o

,. The NRC staff's evaluation of the North Anna Power station, Units 1 and 2 Steam Generator Supports is presented in Section 5.4.2 of Supplc: rent Nos. - 3 and 6 of the llorth Anna l'ower Station, Units 1 and 2 Safety Evaluation Report (Enclosures 7 and 8, respectively). Information concerning the insulation" tent" design provided by VEPC0 is presented in Enclosure 9 - Steam Generator and Reactor Coolant Pump Supports and Enclosure 10 - Letter dated November 19, 1976 to Mr. Bernard C. Rusche, Director, Office of Nuclear Reactor Regulation frcm Sam C. Brown, Jr., Vice President, Power Section, Engineering and Construction, Virginia Electric and Power Company. Information concerning the design of the insulation " tent"was also presented by VEPC0 in Enclosures 4, 5, and 6. Question 10 Have these modifications been finally approved? At what stage of construction are they now, and when should they be completed? i

Response

NRC approval of the heating system design was not required. The applicant was, however, requested to provide analyses showing that increasing the support mc=ber tcmperature did not produce unacceptable strength loss in the heated structures or any other undesirable effects. These analyses have been reviewed and found satisfactory. The heating systems have been installed and tested with 2atisfactory results. Questien 11 Is the brittle-fracture prnblem present in all North Anna units? If not, which ones are not involved? Is it present at Surry? Which units there are affected?

Response

The component supports in North Anna Units 3 and 4 and in Surry Units 1 and 2 are of a completely different design and utilize different uateriais The conclusions regarding the North Anna Units.1 and 2 design, materials and fabrication deficiencies are not applicable to the North Anna Units 3 and 4 and Surry Units 1 and 2 support structures. 2084 009-

P ~,... ~ ~.... Question 12 . Did VEPC0 at any time indicate when it first became awaie of the existence of the enclosed document? If so, when, by its account,.was it first aware of it?

Response

Yes, by VEPCO's account, they were made aware of the document during the litigatien with Sun Shipbuilding and Dry Dock Co. This was during the spring 1976. As stated on Page 9 of the Office of Inspection and Enforcement Report flo. 50-338/77-3 and 50-339/77-2 (See Enclosure 2), the CC-81 analysis viewed by the Office of Inspection & Enforcement, Region WL :. cocrletd and filed within Stone and l!cbster. All individuals inter-their kno..ladge DC-81 was never sent to VEPC0, either formally or informally,. The !! orth Anna Project Documentation Files at Stone and '.!cbster for the period of May 1973 through June 1974 and the entire North Anna Project G Documentation Files at VEPC0 from the inception of the project to December 1976, was examined by the Of fice of Inspection S Enforcement, Region II, i and no correspondence was located that indicated that DC-81 was emr trans-mitted to VEPCO by Stone and !!ebster. "o evidence was uncovered that this report was discussed at any interface meetings between VEPCO and Stone and klebster nor being formally transmitted to the !!RC. suestion 13 Is the Commission now pursuing or considering any proceedings, imposition of. penalties or fines, or other action against VEPC0 as a result of delay or failure to inform the Commission about the ilorth Anna brittle-fracture problem?

Response

No. 2084 010

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