ML19224C797
| ML19224C797 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/09/1979 |
| From: | Polk P Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907060481 | |
| Download: ML19224C797 (9) | |
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NUCLE AR REGULATORY COMMISSION
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Mr. George T. Derry Director, Technical Development General Manager and Chief Programs Engineer State of flew York Energy Office Power Authority of the State Agency Building 2 of fiew York ErTire State Plaza 10 Color. bus Cirtle Albany, fJew York 12223 flew Yor), fl. Y.
In019 Ost. ego County Office Building Lewis R. Bennett, Assistant General 46 E. Bridge Street Manager /Genere l Counsel Oswego, New York 13126 Power Authority of the State of New York George M. Wilverding, Licensing Supervisor 10 Colur. bus Circle Power Authority of the State of New Ycrk New York, New York 10019 10 Columbus Circle New York, New York 10019 Mr. Peter W Lyon Mdnager-NuClea, Opera tions Mr. Robert Deyie Power Authority of the State County Planning Board o' New York Cozty Bui u!ing 10 Colurbus Circle 46 E 3 ridge Street New York, New York 10019 Owego, New York 13126 Mr. J. D. Leonard, Jr.
Mr. Paul Merges Resident Manager fNiYork State Department of Jar.es A. Fitzpatrick Nuclear Power Encironmental Conservation Plan.
44 hoiland Avenue P. O. Box 41 Western New York Service Group Lyceming, %w York 13093 Albany, New York 12208 Docket File G. Kni ghton T. Elsasser, Reg. I NRC PDR A. Schwencer M. Ernst Local PDR D. Ziemann M. Malsch NRR Rd9 P. Check R. Goddard ORS #3 Rdg G. Lainas D. Wiggington H. Denton D. Davis C. Nelson E. Case OELD D. Neighbors V. Stello 01&E (3)
R. Architzel, Reg. I D. Eisenhut S. Sheppard K. Abrahar', Reg. I B. Grimes Project Manager B. D. Liaw R. Vollmer ACRS (16)
K. Herring T. Ippoll'o NRC Participants K. Wichman R. Reid TEPA R. LaGrange V. Noonan J. P,u c ha n a n S. Hosford Dr. Austin, H-ll49 R. F ra l ey W. Paulson K. Muchetti C. Kammerer d fdIF J. Guibert J. Fouchard G. Cunninghas H. Thompson J. Scinto d IJIF3Y G. Sauter E. Jordan M. Peranick, I&[
R. DeYoung R. Mattson J. P. Knight R. Vollmer 790706045'(
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, Mr. Jay Dunkelberger New York State Energy Office 2 Rockefeller Plaza Albany, flew York D'2 2.5 Mr. Thomas Olifant Legislative Assistant Legislative Commission on Energy Systems New York State Assembly Box 167 Albany, New York 12248 Mr. Herbert Van Schaach Oswego County Building 46 E. Bridge Street Oswego, flew York 13125 Ms. Andria Dravo Subconmittee on Energy and Envi ronment 1327 Longworth Avenue Washington, D. C.
20515 Mr. Frank R. Church Town of Scriba Scriba Municipal Buildino R. D. #3, Creamery Road Box 76 Oswego, New York 13126 Mr. James Best, Chairman R. D. 7 Bestview Drive Fulton, flew York 13069 Mr. Robert D. Vessels, Director Office of Environmental Planning New York Sta r Public Service Cornission New York State Enpire Plaza Albany, flew York 12223 Mr. Thomas Cashman Environmental Conservation Department 50 Wolf Road Albany, New York 29/
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NUCLE AR REGULATORY COMMisslON 1
W ASHiNGTON, D. C. 20555 I /
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May 9, 1979
%.1...f Docket No. 50-333 MEMORANDUM FOR-Victor Stello, Jr., Director, Division of Operating Reactors F R O." -
Philip J. Polk, Project Manager, ORB <3, DOR THRU:
Brian K. Grimes, Assistant Director for Engineering and Projects, Divison of Operating Reactors SUDJEET:
OPEN MEETING OF APRIL 10, 1979 WITH THE POWER AUTHORITY OF THE STATE OF NEW YORK REGARDING SAFETY RELATED PIPING RE-ANALYSIS FOR THE JAMES A. FITZPATRICK NUCLEAR PLANT In order to ensure the flow of information regJrding the James A. FitzPatrick Nuclear Plant safety related piping re-analyses, the NRR staff visited the Stone & Webster Engineering Corporation's Boston office on April 10, 1979.
The purpose of the meeting was threefold:
(1) to discuss with the Power Authcrity of the State of New York (PASNY) the status of the re-analysis, (2) to discuss with both PASNY and Stone and Webster (S&W) the technical information requirements as specified in NRC letter of April 2,1979, and (3) to cite available drawings, calculations, procedures, etc.
for work completed to date.
The meeting agenda, enclosure (1), delineates the technical areas discussed.
Meeting atteadance, enclosure (2), consisted of staff personnel as well as PASNY and S&W representatives.
Although the first portion of the visit consisted of an informal technical information meeting open to public observation. no public representatives were present.
The staff requested clarification of the af fected safety related systems as previously identified during the March 26, 1979 site visit. PASNY once again indicated that there were seventeen systems which had been analyzed using the Pipe Stress-Shock 11 code.
However, the number of cemputer calculations was revised from 96 to 95.
The staff indicated that reactor and containment penetrations, and non-safety related piping as i t ef f ects safety related piping, may be considered.
PASMY indicated that calculations are being performed on a prioritized basis having been grouped into the following three categories:
(1) Quality group A systeris which are. or form a part of, the reactor coolant pressure boundary, (2) Systm necessary to reach cold shutdown, and (3) Other safety related auxiliary systems necessary to nitigate the consequences of an accident.
PAShY did not clari fy whether the staf f should expect sequential submittals of informatior reflecting these priorities.
It was indicated that a forual plan of action and schedule should be forwarded as soon as possible in consonance with NRC letter of April 2,1979.
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Victor Stello, Jr. The progress of the re-analysis was discussed.
The licensee indicated that as of April 10, 1979 a total of 47 piping re-analyses had been completed.
These Shock III calculations reflected verification of as-buil t pipe support locations. Preliminary indications are that one, and possibly two, of these analyses showed significantly increased piping stresses.
(The FitzPatricP allowable stresses are defined by ANSI B31.1 - 1967.) During the meeti ig PASNY indicated that formal weekly subnittals would be made.
Subsequent to the meeting, a significantly dif ferent status indicating 11 complete runs was forwarded by letter dated April 16, 1970 (Enclosure 3).
Although problems have not been identified to date the licensee indicated that three options were being considered:
(1) Re-analysis using the NUPIPE code, (2) Re-analysis using floor response spectra with unbroadened peaks, or (3) Re-analysis by development of new floor response spectra using time history analysis techniques.
The staff indicated that the NRC's final position would be made available upon formal notification of PASNY's intentions as previously requested.
In the interim, the licensee was informed that analysis with unbroadened peaks was not acceptable in the past and would not be acceptable now.
With respect to a time history approach, the staff will verify the licensee's sub-mittal by running the E-pipe computer code.
The licensee was informed that there are no known computer codes at present which have been either verified or grandfathered for structural or piping design.
If this time history approach is taken, the staff will also verify the results by running code cases developed by Brookhaven National Laboratory.
In addition, a time history approach will require an evaluation of building structural modeling techniques and the development and review of artificial time histories. Therefore, the licensee was requested to advise the staff as soon as possible regardin; present intentions.
Also discussed was the PASNY response to the Show Cause Order wherein PASNY requested that LRC recind that portion of the Order which requires that FitzPatrick be placed in a cold shutdown condition.
The response is under staff review.
In the interim, PASNY is proceeding with the re-analysis in anticipation of an unfavorable staff reply.
PASNY was advised to contact D. M. Crutchfield (301-492-8041) regarding the staff response to the Freedon of Information Act request of March 16, 1979.
With respc ct to legal concerns the NRC contacts are G. H. Cummingham (301-442-76'/ b ) and J. P. Murray (301-492-7496 ).
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Victor Stello, Jr. By letter dated March 16 1979 the licensee informed the staff. and requested staff's concurrence, of their plan of action with respect to the shutdown requirement of the Order. The licensee was informed that no PASNY action was required at this time, and that a staff response regarding the interpretatior of the " cold shutdown condition" wording would be forthcoming in the near future.
Upon conpletion of the technical information meeting three analyses were reviewed for modeling techniques:
(1) core spray pump suction piping, (2) RHR pump suction piping, and (3) service water to RHR heat exchangers.
The distribution of dynamic mass points was consistent with the criteria spqcifiec in the FSAR (S to 10 f t. segments) and is considered adequate The to represent the dynamic characteristics of these piping systems.
support points were modeled as rigid points in the analysis and valves were modeled as infinitely stif f members with motor operators modeled as eccentric masses. The response spectra were developed using the frequency response method as discussed in the FSAR. For the purposes of the reanalysis, the response spectrum peaks were broadened to account for inaccuracies in their development.
In conclusion, the staff indicated that the PASNY schedule and plan of future action is of high import, and that the staff will be responsive to the receipt of informatior. when received.
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N /l-Philip J. Polk, Project Manager Operating Reactors Branch *3 Division of Operating Reactors
Enclosures:
As staten lf f
AGENDA James A. FitzPatrick Show Cause Order - Pipe Stress Meeting of April 10, 1979 9:00 A.fi.
I.* Introduction A.
Meeting Participants, Purpose and Scope (NRC)
C.
Agenda Summary (NRC) 9:15 % )
th II.* Pipe Stress Re-analysis Status A.
Affected System Identification (PASNY)
B.
Shift / Cum Progress:
Stress Analysis Tabulation (PASNY)
C.
Information Letter of 4/2/79 (NRC)
D.
Plan of Action and Schedule (PASNY)
E.
Response to Show Cause Order (NRC)
F.
Response to FOIA request of 3/16/79 (NRC)
G.
Response to Hydro Test request of 3/16/79 (NRC)
III.
Review of Available Inforration (S&W) 10:15 A.M.
(Lunch Break) 4:00 P.M.
IV.
Conclusion and Closing Cor nents (NRC)
- Open to public observation 2h[
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APRIL 10, 1979 Meeting Attendance
- NRC P. J. Polk W. A. Paulson J. R. Fair A. fl. Fasano (l&E)
W. T. Russell G. H. Cunningham (0 ELD)
L. Tripp (I&E )
PASilY G. T. Berry J. R. Schneider J. D. Leonard, Jr.
J. Helland S&W L. D. Barnes U. A. Ma tson
- Pa rtial Lis tin';
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLuwsus CIRCLE NEW YORK N. Y.10019 (212) 397 6200 GEORGE 7 BEmmy TRUSTEES S E SCWT1v t OstECTOs F 4EDERICK M CLAAR
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y JCsEPH m.sCHulECER Ca.itP t.alsega n mlC H A N D M. FLYNN JOHN W SCSTON nCetRT I W ILLC N ZI Die.c'on or Powete optmatson g April 16, 1979 WW I L L i & M F LUCCY Twoo,,,.Ce. N s,,
JPN-79-19 Director of Nuclear deactor Regulation U.S.
Nuclear Regulatory Ccemission Washington, D.
C.
20555 Attention:
Mr. Thcmas A.
Ippolito, Chief Operating Reactors Branch No. 3 Division of Cperating Reactors
Subject:
James A. Fit: Patrick Nuclear Power Plant Piping Stress Reanalysis - Plant Shutdown
Dear Sir:
Attached for ycur information is a report of the s ta tus of the Stone & Webster piping teanalysis effort, as of April 12, 1979.
This is the first in a series of weekly reports which will be provided to you in accordance with the verbal recuest of G Russell and P.
Polk of the Nuclear Regulatory Core ision during our meeting with them at the Stone & Webster offices on April 10, 1979.
Very truly yours, c'. t J.
R. Schmieder Chief Engineer bo\\
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d JAMES A.
FITZPATRICK NUCLEAR POWER PLANT PIPE STRESS REANALYSIS STONE & WEBSTER ENGINEERING CORP.
STATUS OF WORX AS OF APRIL 12, 1979 Pipinc 1.
Total number of piping reanalyses to perform.
35 2.
Number of reanalyses completed and pipe stresses determined to be within allowabic limits.
11 3.
Number of reanalyses comoleted and pipe stresses determined to above al.lowable limits.
O Pipe Containment Supports Nozzles Penetrations 1.
Total number of ccaponents 1156 82 44 to analyze.
2.
Number of reanalyses complete 7
0 0
and loads determined to be within allowable limits.
3.
Number of reanalyses complete 0
0 0
and loads determined to be above allowable limits.
Est mated date of interim request to NRC for plant i
start-up.
(later Estimated date of final request to NRC for plant start-up.
June 20, 1979*
- This estimate is based on the assumption that no modifications will be required that will af fect plant start-up.
It represents our estinate of the earliest possible date on which our final submittal can be T.ade.
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