ML19224C681

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Summary of 790504 Meeting W/Util in Bethesda,Md Re safety-related Piping Reanalysis
ML19224C681
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 05/18/1979
From: Polk P
Office of Nuclear Reactor Regulation
To: Stello V
Office of Nuclear Reactor Regulation
References
NUDOCS 7907060047
Download: ML19224C681 (15)
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c, UNITED STATES

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7, NUCLE AR REGULATORY COMMISSIC'J

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%.....,y Mr. George T. Cerry Di rec to r, Technical Development General Manager and Chiet Programs Engineer State of New York Energy Office Power Authority of the State Agency Building 2 of New York Empire State Plaza 10 Columbus Circle Albany, New York 12223 flew York, N.

Y.

10019 Oswego County Office Building Lewis R. Bennett, Assistant General 46 E. Bridge Street Manager / General Counsel Oswego, New York 13126 Power Authority of the State of New York George M. Wilverding, Licensing Supervisor 10 Colurbus Circle Power Authority of the State of New York New York, New York 10019 10 Columbus Circle New York, New York 10019 Mr. Peter W. Lyon Manager-Nuclear Operations Mr. Robert Deyle Fouer Authority of the State County Planning Board of New York County Building 10 Colurbus Circle 46 E. Bridge Street New York, New York 10019 Oswego, New York 13126 Mr. J. D. Leonard, Jr.

Mr. Paul Merges Resident Mu.lagE r New York State Department of James A. Fitzpatrick Nuclear Power Environmental Conservation Plant 44 Holland Avenue P. O. Box 41 Western New York Service Group Lycoming, ',ew York 13093 Albany, New York 12208 Docket File G. Kni ghton T. Elsasser, Reg. I NRC POR A. Schwencer M. Ernst Local POR D. Z;emann M. Malsch NRR Rdg P. Check R. Goddard ORS #3 Rdg G. Lainas D. Wiggington H. Denton D. Davis C. Nelson E. Case OELD D. Neighbors V. Stello OI&E (3)

R. Architzel, Reg. I D. Eisanhut S. Sheppard K. Abraham, Reg. I B. Grimes Project Manager B. D. Liaw R. Vollmer ACRS (16)

K. Herring T. Ippolito NRC Particicants K. Wichman P. Reid R. LaGrange V.

Noonan J. Suchanan S. Hosford Dr. Aus tin, H-ll49 R. Fraley W. Paulson K. Muchetti C. Kammerer J. Fair, J. Guibert J. Fouchard G. Cummingham H. Thompson J. Scinto J. Murray G. Sauter E. Jordan M. Peran.ck, I&E R. DeYoung R. Mattsor, J. P. Knight R. Vollmer 0$

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. Mr. Jay Dunkelberger New York State Energy Office 2 Rockefeller Plaza Albany, New York 12223 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 Building R. D. #3, Creamery Re d Box 76 Oswego, New York 13126 Mr. James Best, Chairman R. D. 7 Bestview Drive Fulton, New York 13069 Mr. Robert D. Vessels, Director Office of Environmental Planning New York State Public Service Connission New York Sta te Enpire Plaza Albany, New York 12223 Mr. Thomas Cashman Environmental Conservation Department 50 Wolf Road Albany, New York n c a.'

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.a R E C j-N UNITED STATES g

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Docket No. 50-333 MEMORANDUM FOR:

Victor Stello, Jr., Director, Divisf or. of Ope-ating Reactors, DOR FROM Philip J. Polk, Project Manager, ORS =3, D0R

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THRU:

Brian K. Grimes, Assistant Director for Engineering 7<

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and Projeces, DOR

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SUBJECT:

OPEN MEETING OF f4AY 4,1979 WITH THE POWER AUNORITY OF THE STATE OF NEW YORK REGARDING SAFET) R ELAI ED PIPING REANALYSIS FOR THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT On May 4, 1979, at the request of the Power Authority of the State of New York (PASNY), an open mceting was held in Bethesca in order to dis-cuss:

(1) The status of th-James A. FitzPatrick safety related piping seismic reanalysis, and (2) The PASNY approach to developing a safety analysis to allow plant startip by June 10, 1979.

In addition to staff and licensee personnel, attendance included General Electric and Stone a Webster representatives (Enclosure 1).

By letter cated April 30, 1975 PASNY provided a listing of piping which was analyzed using the Shock II Computer Code and which is r.ow in the process of being reanalyzed (f nclosure 2). (PASNY prcvided narked-up system drawings reflecting th subject 17 safety related systems and tM 96 computer runs.) An in 'croal status was presented which reflected werk acccmplished to date (Fr.:losure 3).

This status reflected neither Quality Assurance by the Ston? & '..'ebster New York office nor a verifi-cation of system layouts by FitzPatrick site personnel.

(Personnel from the Office of Inspection a-'d Enforcement visited the FitzPatrick plant the week of April 30, 1979 to review system layouts as-buil t. )

Peak broadening was used in the reanalysis. The staff recuested that a listing of completed reanalyses, including quality assurance and as-built verification, be provided as soon as possible.

Upon receipt, Operating Reactors ;ersonnel will schedule a meeting to rev ew the i

Stone i Webster analyses and I&E will visit the site to verify system layout.

Upon c:maletion of reanalysis status discussions, a cresentation was made of the Fitz?atrick approach to allow interin :lin c:e at:n (Enclosure 4).

General Electric is performing a safet; e.a ua: ion to o n t.

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s ya m o t

t

Victor Stello, Jr. justify plant operation prior to completion of the reanlaysis.

In essence, either of the two proposed options.'equire an analyses of accidents and transients with less than all safety related systems assumed available. Af ter the GE presentation of these options, the staff provided a preliminary response regarding the acceptability as well as pitfalls of each approach. The staff indicated Onat significant delays will be encountered if the GE analyses result in:

(1) A licensing amendment and/or exemption, (2) A core de-rate, (3) An increase of the probability of an accident, or (4) A dacrease in safety margins. PASNY indicated that Option 1 will require 66 runs to be reanalyzed and Option 2 requires 80 reanalysis runs.

~he staff provided the following documents to clarify pi;ing cesign margins:

(1) NUREG/CR-0098, " Development of Criteria for Seismic Review of Selected Nuclear Power Plants, (2) Cornell tad Newmark paper, "On the Seismic Reliability of Nuclear Power Plants, and (3) ANS paper,

" Proceedings of the Second Pacific Basin Conferer

'$ on Nuclear Power Plant Construction, Operation and Development.'

addition, the staff suggested that PASNY obtain and review the transcripts of Commission meetings dated April 26,197' and May 3,1979, for guidance co using i

SSE as a basis for restart.

In conclusion, PASNY indicated that the staff would be acvisec daring the week of May 7, 1979 regarding the timing of the Stone & Weoster New York office v ' sit.

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J Philip J. Polk Project Manager Operating Reactors Branch +3 Division of Operating Reac tors

Enclosures:

As stated

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Enclosure (1)

ATTENDEE 3 James A. Fit: Patrick f'eetino of vav

. 1979 Safety Related Pioing Seismic Re-Analysis PASNY J. Helland R. Rajaran J. Leonard F. Early J. Daincra (Consul tant)

_GE L. Zull J. Cleveland S&W F. Dymak J. '!celxen L. Barnes A. Greenfield NRC P. Polk W. Russell J. fiartore B. D. Liaw K. Wichman K. Herring J. Fair R. LaGrange W. Paulson m4 _,p,,. v.

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nc' :ure. ;j James A. Fi czPatrick Informal Re-analysis Sta tus i

A.

Ploinc (1)(2) 1.

Number of Piping Re-analysis 96 l

2.

Number of Re-analyses Ccmpleted 58 l

3.

Number of Re-cnalyses Above Allowable 0(3) 4 Approximate Precentage with Increased Stress 1/3 Ccmoorents (1) b Pipe Succorts Nozzles Penetrations 1

Number to Analyze 1156 87 55 l

2.

Number Completed 350 10 4

3.

Number above Allowable 0

0 0

4, Approximate Percentage j

with Increased Load 1/2 6/10 0

Footnotes (I)Does not reflect Quality Assurance by Stone & Webster New York Office.

(

j Oots not reflect verification of as-built system layouts by FitzPatrick site i

pe rsonnel.

(3)The Core Spray Systen was reviewed by the Option Review Committee.

/

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.n o To allow interim operation until compl e te se'sric ;iping reanalysis can be completed OPTION 1 - Reactor coolanc pressure boundary is veri fied to be

';-i c h re ta i ns th:

seismically qualified, but pipin; containment integrity has not beer s e i s-i c a l l y reanal /:ed and/or v-ri"ied

-.q r,

on.12

1. Seismic event will not cause a i c s s-:f -cc ol a n t ar.cident because RCPB is sei smi cally qualified
2. Cold shutdown can be achieved a ':e r a seisnic event because sufficient s a f e t ;. sy s ten:s a re avail a ble which have been seismically cualified ASSU"?TIONS:

1 Desicn basis earthquake and 5 _::' d:

r. o t occur

_A simultaneously (probacility cf c : c u r -a n c e ~ : 0

)

2. '..' o r s t single f ail ure will also be ascured C P T : C'.

2-Reactor coolant pressu re bounda ry his c:t been seisnically reanalyzed and/or verified, but piping which retains containment integrity is seismically cualified APPROACH:

Parametric studies will be conducted to deternine the power level at which tne plant can o p e ra t e anc not violate any safety lirits. a Ieis ic2: 1 induced

-.. '.n - c"m'vv"-o_m

. i t. h

e. n '..

in'._r c._=~_.

.c-r s e i S ~ i C S I '.' Cualified m A

'..h.,

J, 4

,3 6

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Q %,v %v

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sn 1

A seismic event may cause a LOCA with pipe break area (s)

)

corresponding to the RCPE pipe (s) that have not been seismically qualified 2.

Eased on the assumed total break area a r.d t he a va il a b il i ty i

l of seismically qualified safety systers, a maximum allcwable power level will be calculated C.y ' r.+ D e c.

L.

.n.

Assur' g ADS, LPCI, containment cooling

d e o f R'#R a n d ~.a ;. e u p water systems are seismicall; q u a '. i f i e d Then total break area (s) will be determined fo r the g

following RCPS lines (individually, or in various Combinations)

!/.a i n steam lines (outside the ccntainment) c Feedwater
Core spray c Control red drive return i ine e Reacter 'ater cleanup syster suction 1lna

[

To determine the pcwer level at which the plant can operate and not viciate any LOCA safety a n a l y s i s l i r.i t s if a seismically induced LOCA occurred m e c m.... I Inns.

.i.

f The iiritinc scismic ever.. (DEE) is a s s ur:e d

2. Seismic event independent of design basis LOCA 3.

Recirculation lines are seismically qualified and will e.

s,- o. f'...

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e 4 W,

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3 i

5.

The naxinun breaP area (s) and loca:ior.;s', a r e l i.- i t e d by the criteria that the resul ting conta inmen: Icads P

t and reactor internal pressure dif~erences.111 not L

exceed allowa bl e val ues.

i

7. Offsite co..er will be assumed not a v aila bl e o.

i he most liniting s i n g l e f a i,i u r e

'.,1,61 be assuned t

i 9

The calculations will conform to the requi e=ents of l

10CFR50 15 A;uendix K,

except that al' pi:ing which has-i been s e i s m i c 3 i l.v cualified is 10 :,:su :c tc :reas RESULTS:

t,.

l 1.

Event description e Erea' area (s). location (s) i c,in1.ing Single rctive rallure ( :s. - 3 r,

f e Systems remaining 2.

Analysis results C

a. c -

v i

..3L..--non t,

nn.

r

~

c Reactcr po>er level C0"r.L"S'9<",.c.'

n-e Option 2 analyses will show tna limi tad seismically j

qualified safety systems are adequcte to nitigate c

~

seismically ini tiated accidents o Therefore, plant can be operated safely at X" O f rated po'.ce until a conciete seismic piping reanalysis is cc eted, and changes and/or "cd i '1 ca ti on s t the piar.:

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