ML20133H525

Advises of Status of 831028 Commitment to Adjust Code Safety Valves to EPRI Ring Setting.Analytical Work Performed by CDI to Obtain Optimum Ring Settings & Couple Code Validated Against EPRI Data.Sser Supporting Safety Valve Tests Encl

ML20133H525
Person / Time
Site:	Crane
Issue date:	03/04/1985
From:	Hukill H GENERAL PUBLIC UTILITIES CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20133H476	List: ML20133H525 ML20133H563 ML20133H577
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 0187A, 187A, 5211-85-2046, NUDOCS 8508090380
Download: ML20133H525 (8)

Text

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GPU Nuclear Corporation N g g.g{

Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:

j March 4, 1985 5211-85-2046 Office of Nuclear Reactor Regulation Attn:

J. F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.

20555 Cear Mr. Stolz:

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Safety Valve Ring Setting By letter dated October 28,1983(5211-82-260), GPUN comitted to adjust the code safety valves, at THI-1 to the EPRI ring setting in order to bound TMI-1 by the EPRI test results.

Since that time, GPUN has had analytical work perfortned by CDI through the B&W Owners Group to obtain the optimum ring settings for the Dresser safety valves used at TMI-1.

In order to quantify the installation constraints for satisfactory valve operation, EPRI sponsored the development of a spring loaded safety valve dynamic model coupled to the unsteady motion in the upstream piping system resulting in the COUPLE Code.

The results of this code have been validated against applicable EPRI test data for Dresser valves and the code has been shown to be reliable in predicting valve stem position, stability and percent blowdown across the range of tested steam pressurizer pressures valve ring settings, back pressures and piping configurations. The valve model developed incorporates the major geometrical and physical valve features (including spring rate) to predict valve performance in response to changes in mass flow l

rate and internal pressure forces acting within the tested valve types.

Stable valve performance at THI-1 (including mass flow rates and percent blowdown) is predicted for a middle ring setting of -50 notches for the Dresser 31739A for a back pressure of 700 psig and steam inlet pressures between 2500 and 2750 psig. The lower ring setting was specified by B&W in accordance with Dresser recomendations for providing ample clearance between the lower ring and the disc holder when the valve is closed. Therefore, TMI-1 plant specific ring settings are as follows:

G508090380 850806 Lower ring + 8 notches PDR ADOCK 05000289 Middle ring -50 notches F

PDR Upper ring -48 notches GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

r 2-5211-85-2046 The reports describing the analyses performed to predict pressurizer safety valve performance during relief conditions of steam and water for Dresser Industries Model 31739A are available on site for review.

Further, GPUN has performed a 10FR50.59 evaluation of the ring settings and determined that there is no unreviewed safety question or Tech. Spec. Change required.

Sincerely, H. D.

kill Director,THI-1 HDH/LWH/lr:549e cc:

R. Conte J. Van Vliet Reference - NRC ltr 9/29/81 GPUN ltr 12/3/82 (5211-82-257)

NRC ltr 9/9/83 GPUN ltr 9/9/83 (5211-83-242)

NRC ltr 8/22/84 0187A 3

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NUCLEAR REGULATORY COMMISSION s

namaworow.o.c.aosse May 14,1985 Docket No. 50-289 Mr. Henry D. Hukill, Vice President and Director - TMI-1 GPU Nuclear Corporation P. 0. Box 480 Middletown, Pennsylvania 17057

SUBJECT:

SUPPLEMENT TO SER FOR THREE MILE ISLAND, UNIT 1 SAFETY AND RELIEF VALVE TESTING, MUREG-0737, ITEM II.D.1 Previously you comitted to adjust the ring setting of your Dresser Model i

31739A code safety valves at TMI-1 so that they would be bounded by the Electric Power Research Institute (EPRI) test results.

By letter dated March 4, 1984 you provided new ring settings based on an analysis performed by Continuum Dynamics Inc through the BW Owners Group.

One of the important considerations in the performance of safety valves is the specific ring setting adjustment. As indicated in the attached supplementary Safety Evaluation, the new ring settings for the TMI-1 safety valves have been shown to produce full lift and stable valve operations for steam discharge and be bounded by the EPRI test results. Therefore, we find that the information submitted demonstrates the ability of the safety valves to function under expected operating conditions for design basis transients and accidents as defined under NUREG-0737. Item II.D.1.

Sincerely, l

J in F. Stolz, Chi f l

0 rating Reactors ranch #4 tvision of Licensing cc: See next page c'A Mrf a n n __

m p_.<ig s t r b

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e, to SUPPLEMENT 70 SAFETY EVALUATION REPORT TMI ACT!0N--NUREG-0737 (II,0,1)

RELIEF AND SAFETY VALVE TESTING THREE MILE ISLAND UNIT 1 DOCKET NO. 50-289 PAY 1985 1

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Introduction In the TMI-1 SER for NUREG 0737, Item II.D.1, Performance Testing of Relief and Safety Valves, the applicability of the testing performed by the Electric Power Research Institute (EPRI) to the TMI-1 safety valves is discussed. One of the important considerations in the perfomance of the safety valves is the specific ring setting adjustment.

In a letter (Reference 1) dated October 28, 1983 GPUN consnitted to adjust the ring setting of the Dresser Model 31739A code safety valves at THI-1 so that they would be bounded by the EPRI test results (Reference 2). Reference 3 presents the ring settings for the TM!-1 safety valves.

The rin were based on an analysis performed by Continuum Dynamics Inc. (g settingsCDI) thro the 54W owners group (see Reference 4).

This supplement to the Safety Evaluation Report in the TMI-1 relief and safecy valve testing presents an evaluation of the ring settings based on a review of the CDI report (Reference 4) and the EpRI safety and relief valve test report (Reference 2).

Evaluation of TMI-1 Ring Settinos COI used the valve dynamics simulation code COUPLE, which they validated against the EPR! safety valve test data (Reference 2), to optimize the ring settings of six B&W nuclear plants for steam discharge, including Three Mile Island Unit 1.

The study optimized the ring settings for the expected range of inlet-and back-pressures under steam discharge conditions.

The resulting ring settings for TM!-1 are:

Upper, ring

-48 notches Middle ring

-50 notches Lower ring

+ 8 notches Reference 2 contains infor1 nation for five tests that bound the THI-1 ring settings.

l Tests 322 and 324 have middle ring settings of -40 and -60 which bound the TMI-1 middle ring setting of -50.

The test backpresssures were 609 psia and 664 psia respectively.

Both tests were stable and exhibited full lift, full j

discharge, and blowdowns of 11.15 and.12.65 respectively.

I A comparison between tests 322. 324 and 1011 demonstrated that valve performance is not sensitive to lower ring settings.

The 1cwer ring settings were +11. +11 and +5 respectively, which bounded the TMI-1 lower ring setting of +8, and produced similar stable results.

Test 320 demonstrated the effect i

of backpressure on valve If ft and discharge.

With a 866 psia backpressure, l

valve lift during Test 320 was 44% of rated and discharge was 64t of rated.

l However, valve -performance was stable.

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- -- -,,,,,., - n..,-

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.i The results of tests 322, 324, 326 and 1011 demonstrated that full lift. full discharge and stable valve operation is achieved with back pressures between 196 psia and 669 psia which bounds the TMI-1 back pressure of 500 psia.

Conclusion The ring settings for the THI-1 safety valves have been shown to produce full lift and stable valve operations for steam discharge conditions by analysis and by comparison with the EPRI test results.

Therefore, we find that the information submitted demonstrates the ability of the safety valves to function under expected operating con.ditions for design basis transiants and accidents as defined under NUREG 0737. Item !!.0.1.

Reference _s

1. J. F. Stolz, NRC from H. D. Hukill, GPU Nuclear, 5211-83-260, October 28, 1983.

2. EPRI PWR Safety and Relief Test Prooram Safety and Relief Valve Test Report. EPRI hP-2628-5R, Decemoer 195Z.

3. J. F. Stolz NRC from H. D. Hukill, GPU Nuclear, 5211-85-2046, March 4,1985.

4. Safety Valve Dynamic Analysis for Dresser Industries' 31739A and 3:Jb5A valves, Rev.l. Preparea oy Continuum Dynamics, Inc., for Babcock and Wilcox,C.D.I.

Report No. 83-4,. December 1983.

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SERVICE LIST Nunzio J. Palladino, Chairman Administrative Judge 1

l U.S. Nuclear Regulatory Commission Gustave A. Linenberger, Jr.

Washington, D.C.

20555 Atomic Safety and Licensing Board j

U.S. Nuclear Regulatory Commission, Thomas M. Roberts, Commissioner Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Administrative Judge

~

Gary J. Bdles James K. Asselstine, Commissioner Chairman, Atomic Safety and U.S. Nuclear Regulatory Commission Licensing Appeal Board Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 i

Frederick Bernthal, Commissioner i

U.S. Nuclear Regulatory Commission Administrative Judge Washington, D.C.

20555 John R. Buck

)

Atomic Safety and Licensing l

Lando W.

Zeck, Jr., Commissioner Appeal Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commissior l Washington, D.C.

20555 Washington, D.C.

20555 Administrative Judge Administrative Judge Ivan W. Smith Christine N. Kohl 1

Chairman, Atomic Safety and Atomic Safety and Licensing Licensing Board Appeal Board U.S. Nuclear Regulatory Commission U.S.

Nuclear Regulatory Commissiot-Washington, D.C.

20555 Washington, D.C.

20555 Administrative Judge Docketing and Service Section 'c3)

Sheldon J. Wolfe Office of the Secretary Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commissior,

U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Washington, D.C.

20555 Atomic Safety and Licensing Mr. Henry D.

Hukill Board Panel Vice President U.S. Nuclear Regulatory Commission GPU Nuclear Corporation Washington, D.C.

20555 P. O.

Box 480 Middletown, PA.

17057 Atomic Safety and Licensing Appeal Board Panel Mr. and Mrs. Norman Aamodt U.S. Nuclear Regulatory Commission 200 North Church Street i

Washington, D.C.

20555 Parkesburg, PA.

19365 f

Jack R. Goldberg, Esquire Mrs. Louise Bradford Office of Executive Legal Director TMI ALERT U.S. Nuclear Regulatory Commission 1011 Green Street i

Washington, D.C.

20555 Harrisburg, PA.

17102

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SERVICE LIST Page 2 Thomas Y. Au, Esquire Joanne Doroshow, Esquire Office of Chief Counsel The Christic Institute Department of Environmental 1324 North Capitol Street Resources Washington, D.C.

20002 505 Executive House P. O. Box 2357 Lynne Bernabei, Esquire Harrisburg, PA.

17120 Government Accountability Project Michael F. McBride, Esquire 1555 Connecticut Avenue LeBoeuf, Lamb, Leiby & MacRae Washington, D.C.

20036 1333 New Hampshire Avenue, N.W.

Washington, D.C.

20036 Ellyn R. Weiss, Esquire Harmon, Weiss & Jordan Michael W.

Maupin, Esquire 2001 S Street, N.W.,

9430 Hunton & Williams Washington, D.C.

20009 707 East Main Street P. O. Box 1535 William T. Russell Richmond, VA.

23212 Deputy Director, Division of Human Factors Safety Office of NRR Mail Stop AR 5200 U.S. Nuclear Regulatory Commissi Washington, D.C.

20555 s