ML20050B605

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Submits Preliminary Evaluation of PWR Safety & Relief Valve Test Program,In Accordance w/NUREG-0737,TMI Action Item II.D.1.EPRI Test Program Representative of Facility Design. Extension of 820701 Final Evaluation Deadline May Be Needed
ML20050B605
Person / Time
Site: Summer 
Issue date: 04/01/1982
From: Nichols T
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204060121
Download: ML20050B605 (12)
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Text

{{#Wiki_filter:r e o SOUTH CAROLINA ELECTRIC a gas COMPANY post orrier son 7s4 g CotuMaiA, south CAROLINA 29218 k b gg T. C. Nic wots. J n. ' /.s April 1, 1982 'O v.oeu......o ,o = = g n y,, s =me.. on-.. Mr. Harold R. Denton, Director pnn A. _3 n r h O: G02A ~~ Office of Nuclear Reactor Regulation 9 U. S. Nuclear Regulatory Comission A ~ Washington, D.C. 20555 A C

Subject:

Virgil C. Surmer lear: St$ tion Docket No. 50/395 PWR Safety and Relief Valve Test Program Plant Specific Submittal Letter 'IMI Item II.D.1

Dear Mr. Denton:

In accordance with the initial recomendations of NUREG 0578, Section 2.1.2 as later clarified by NURai 0737, Item II.D.1 and the USNRC letter dated September 29, 1981, each Pressurized Water Reactor (PWR) utility on or before April 1, 1982, was to submit a preliminary evaluation supported by test results which denonstrates the capability of relief and safety valves to operate under expected operating and accident conditions. This letter is the South Carolina Electric and Gas Ccapany (SCE&G) response to the April 1, 1982, USNRC submittal request and is applicable to the Virgil C. Sumer Nuclear Station. SCE&G is a participant in the Generic PWR Safety and Relief Valve Test Program inplemented by the Electric Power Research Institute (EPr.I) at the request of participating PWR utilities in response to the USNBC recomendations for safety and relief valve testing. The primary objective of the Test Program was to provide full scale test data confirming the functionability of prinary system power operated relief valves and safety valves for expected operating and accident conditions. The second objective of the program was to obtain sufficient piping thermal hydraulic load data to permit confirmation of nodels which may be utilized for plant unique analysis of safety and relief valve discharge piping systems. Relief Valve tests were coupleted in August, 1981, and safety valve tests were conpleted in Dem=rb r, 1981. The reports prepared by EPRI docunenting the Test Program results are as follows: " Valve Selection / Justification Report" This report documents that of the selected test valves, the safety valves and power operated relief valves installed at the Virgil C. Sumer Nuclear Station are the same as those tested. / i I 8204060121 820401 PDR ADOCK 05000395 P PDR

1 r Mr. Harold Denton April 1, 1982 Page 2 " rest Condition Justification Report" and the " Westinghouse Plant Condition Justification Report" These reports document the basis and justification of the valve test conditions for the Virgil C. Sumer Nuclear Station. Although the analysis has been performed, the " Westinghouse Plant Condition Justification Report" does not include the Virgil C. Sumer Nuclear Station as having the plant specific analysis for Cold Overpressure Protection. This is because the plant condition report preceeded the analysis for the Virgil C. Sumer Nuclear Station. The results of that analysis, shown in Attachment I, demonstrate that the test conditions envelope cold overpressure plant conditions. Currently, a second plant specific Cold Overpressure Protection analysis is being performed by Westinghouse using inproved Power Operated Relief Valve (PORV) operating times. Westinghouse will specifically address plant conditions in relation to test conditions as a part of this analysis. The current analysis effort is anticipated to be couplete in early April and no change in the test conditions enveloping plant conditions is expected. Attachment II to this letter contains a reduced size drawing reproduction of the pressurizer safety valve inlet piping and a tabulation of the piping and ccuponents frcn the pressurizer to the pressurizer safety valve. Conparing the tabulation for the Virgil C. Sumer Nuclear Station piping to the "G" configuration of table 4-2, used in testing our safety valves, it can be readily concluded that the inlet piping configuration tested envelopes the safety valve inlet piping configuration of the Virgil C. Sumer Nuc7 Mr Station safety valves. " Safety and Relief Valve Test Report" This report provides evidence demonstrating the functionability of the l Virgil C. Sumer Nuclear Station safety and relief valves under the t selected test conditions. The tests results for the PORV's conclusively d m onstrate valve operability. Although the functionability of the safety valves has been denonstrated, anmalies in safety valve performance are being addressed by the Westinghouse Owners Group for the Virgil C. Sumer Nuclear Station and other Westinghouse PWR utilities. Although not specifically applicable to each utility, the areas being addressed include: inconsistencies in valve opening; delays in valve opening l l t

Mr. Harold R. Denton April 1, 1982 Page 3 due to water bleed-off; valve chatter on steam opening; extended blowdown; inlet piping pressure oscillations; and identification of parameters required for adjusting ring positions. These studies are funded and in various stages of completion. A EAP will be prepared and is currently scheduled for submittal July 1,1982 with the piping analysis. " Application of REIAP 5/ BOD 1 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Ioads" This report presents an analytical model benchmarked against test data that may be used for the Virgil C. Sumer Nuclear Station plant specific analysis of the safety and relief valve discharge piping system. All of the documents have been received by SCE&G and transmitted to you by David Hoffman of Consuners Power Conpany on behalf of the participating PWR utilities as part of our response neeting the April 1, 1982, preliminary submittal requirement. In addition to providing the referenced reports, SCE&G has performed a preliminary review of the Test Program results. Based on the review, we have concluded that valves tested represent the safety and relief valve designs and that the conditions tested envelope the range of expected operating and accident conditions for the Virgil C. Sunmer Nuclear Station. Also, the above mentioned reports do provide the evidence required by NUREG 0737, Item II.D.1.A which will be used to perform the final plant specific evaluations. The September 29, 1981, USNRC letter requested that plant specific final evaluations be submitted by July 1,1982. In order to meet that date, evaluations have been initiated. Depending on the outcome of the evaluations, it nay be necessary to continue the evaluation beyond July 1,1982. If a longer evaluation period is required you will be notified on or before July 1, 1982. If you have any further questions, please let us know. Very truly yours, T. C. Nichols, Jr. NBC:'IG:lkb Attachments cc: See Page 3

Mr. Harold Denton April 2, 1982 Page 4 cc V. C. Surmer (w/o attach.) G. H. Fischer-(w/o attach.) H. N. Cyrus T. C. Nichols, Jr. (w/o attach.) M. B. Whitaker, Jr. J. P. O'Reilly H. T. Babb D. A, Nauman C. L. Ligon (NSRC) W. A. Williams, Jr. R. B. Clary O. S. Bradham i A. R. Koon M. N. Browne G. J. Braddick J. C. Ruoff J. L. Skolds J. B. Knotts B. A. Bursey M. Z. Lee D.' T. Klinksiek NPCF File

l ATTE.HMCNT I SYSTEM COLD OWJTRESSURE PR0rK"rION PORV SETPOINTS i

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9 6 ATT/CHMENT II SAFETY VALVE INLET PIPING CONFIGURATION l l l I 1 I ) l l l l

( Virgil C. Sumer Valve Inlet Piping Configuration IAmngth I. D. (Inches) (Inches) Vessel Nozzle (A)1 9 5.189 Pipe (B) 6 5.189 43' IR ell (C) 6.75 5.189 Pipe (D) 6.5 5.189 90* IR ell (E) 14.14 5.189 Pipe (F) 18 5.189 90* IR ell (G) 14.14 5.189 Pipe (H) 12 5.189 90* IR ell (I) 14.14 5.189 Pipe (J) 5.5 5.189 Safety Valve Flange (K) 8 5.189 "G" Configuration Equivalent Length: 8" N minal Pipe Size = 71 inches 6" Nominal Pipe Size = 117.5 inches i V. C. Surmer Mulvalent Length: 6" Nominal Pipe Size = 114.17 itches 1. Letter designations identify conponents shown on drawings.

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