ML20010A326

Forwards Response to NUREG-0737 Item II.D.1 Re Safety & Relief Valve Testing.Includes Util Rept on Performance Testing & Design Evaluation, Exam & Test of Crystal River 3 Power-Operated Relief & Safety Valves.

ML20010A326
Person / Time
Site:	Crystal River
Issue date:	08/07/1981
From:	Cross W FLORIDA POWER CORP.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML20010A327	List: ML20010A326 ML20010A335
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 3-081-05, 3-81-5, NUDOCS 8108110316
Download: ML20010A326 (10)

Text

-

" kC gs pg'y>g I

I

[ ,YA.}fp Mf Rodda P.o...w..e..r

. r .

August 7, 1981

1. 3-081-05 File: 3-B-5-a ' to Mr. Darrell G. Eisenhut, Director ~ nEl[lft L.

Division of Licensing g7 Office of Nuclear Reactor Regulation - Ea,A U %G l 0 193  % Nd U.S. Nuclear Regulatory Commission  %=%e., % J-Washington, D.C. 20555  %

Subject:

Crystal River Unit 3 Docket No. 50-302

'M Operating License No. DPR-72 NUREG-0737 - Post TMI Requirements Item II.D.1 - Safety and Relief Valve Test Requirements

Dear Mr. Eisenhut:

In our letter of July 1,1981, regarding the EPRI Safety and Relief Yalve Test Program, we indicated we would provide you with a plant specific eval-uation of the EPRI interim report and other plant specific data by August 7, 1981. This submittal satisfies that commitment.

Also, NUREG-0737, Item II.D.1 requests:

1. Plant-specific submittal s confirming adequacy of safety and relief valves based on licensee preliminary review of generic test program results,

2. Plant-specific reports for safety and relief qualification, and

3. Plant-specific submittals for piping and support evaluations.

This submittal, in conjunction with the EPRI material referenced in the attached report, satisfies these items.

, The attached report, " Report on Performance Testing and Design Evaluation of Safety and Relief Valves for Crystal River Unit 3" and supporting material present a summary of the testing and operational experience to date on safety and relief valves of the same design as those installed at 8100110316 810807 8 Q PDR ADOCK 05000302 P PDR & f Generai Office 3201 inirty-fourtn street soutn . P.O. Box 14042. st. Petersburg. Florwja 33733 . 813--866-5151 k

! r

. =

A , .

~

., Mr. Darrell G. Eisenhut August 7, 1981 Page 2 Crystal River Unit 3. It also describes the applicwiiity of the EPRI test data to Crystal River Unit 3. Thus, this report shows that the safety and relief valves, as installed at Crystal River Unit 3, are ;ualified to perform their intended function under all anticipated operational transient and accident conditions.

Very truly yours, FLORIDA POWER CORPORATION A$w$.

i i

W. A. Cross Manager Nucler Licensing Cross (R04)3-2 l

.i g

r

[

. . _ . _ . _ . _ _ _ . _ _ _ _ , _ . _ . . _ . . . . . . _ . _ _ . ~ , _ - . . ~ . . _ _ . _ . _ , . , - . _ _ , - _ _ - . . . _ .

i August 1981 i

9 i

-i p 1

! i i REPORT ON PERFORMANCE TESTING AND DESIGN EVALUATION OF SAFETY AND RELIEF VALVES F0R CYRSTAL RIVER UNIT 3 OPERATING LICENSE NO. DPR-72 FLORIDA POWER CORPORATION ,

ST. PETERSBURG, FLORIDA 1

i i

E t

i h

r t

1 i

e b

)

I

TABLE OF CONTENTS i.

4 i

I. INTRODUCTION II. APPLICABILITY OF VALVES TESTED III. EVALUATION OF TEST CONDITIONS IV. EVALUATION OF DISCHARGE PIPING AND EFFECT ON VALVE OPERABILITY i V. CONCLUSIONS i,

VI. REFERENCES e

i I

e i

i i

l l

l l

i Cook (Report)DN108-3 I

=

I. INTRODUCTION Pursuant to the recomendations and subsequent requirements of NUREG 0578 and NUREG 0737, Florida Power. Corporation ccmmitted to participate in the Electric Power Research Institute (EPRI) sponsored Safety and Relief Valve Test Program directed at qualifying the reactor coolant system safety and relief valves under anticipated operating conditions for design basis transients and accidents. By this submittal, herein is presented the results of the Generic EPRI Test Program conducted on or before June 19, 1981, as they apply to Crystal River Unit 3, and the data collected as a result of the Crystal River Unit 3 transient of February 26, 1980. From this data, it can be seen that the operability and integrity of the safety and relief valves and related piping systems at Crystal River Unit 3 is substantiated.

i

{

l l

l l

Cook (Report)DN108-3

II. APPLICABILITY OF VALVES TESTED The valves which have been tested under the EPRI program which are ap-plicable to Crystal River Unit 3 are noted as follows:

A. Safety Valves (Ref.1, Section 2.3.1.b)

"The same basic valve design Model No. 31700, is ured in all PWR plants which have Dresser safety valves. The Dresser valve is a direct acting spring loaded safety va',ve design.

Again, a variety of combination of inlet, outlet and orifice sizes are used in various PWR plants, as shown in Table II-3.

For the tests, two Dresser safety valves were selected, a valve with a .small orifice size, and a valve with a large ort-fice size. Also, the two valves selected for test are the same models and sizes as valves installed in 27 of the 36 PWR plants which have Dresser valves. These valves are briefly described below:

l .31739A This valve model has a small orifice size and flow capacity and is utilized in 10 of the 36 PWR plants which have Dresser safety val ves. . . . "

B. Relief Valves (Ref. 14, Section 2.3.2.e)

"The Dresser models are electrically actuated pilot operated valve designs. As indicated in Table II-4, there are two dif-ferent Dresser valve models utilized in PWR plants: Model 31533VX-30 which utilizes a bellows in the pilot valve section of the valve, and Model 31533VX which does not have a bel-lows. For the test, Model 31533VX-30 was selected since it directly represents 19 of the 21 PWR valves. Also, the re-sults obtained from the Model 31533VX-30 valve represent Model 31533VX valve performance."

The safety and relief valves utilized at Crystal River Unit 3 are, re-spectively, Dresser Industries' 2 1/2" X 6" Model 31739A and Dresser Industries' Model 31533VX-30; therefore, it is seen that the valves selected for testing in the EPRI program are directly applicable to Crystal River Unit 3.

1 i

i l

Cook (Report)DN108-3

III. EVALUATION OF TEST CONDITIONS The conditions selected for testing of the safety and relief valves to meet the recommendations of NUREG 0578, and NUREG 0737, and the test program established by EPRI are as follows:

1) Steam

2) Water

3) Steam to Water (Transition)

4) Water Seal Simulation It should be noted that the water seal simulation condition is not ap-plicable to Crystal River Unit 3 as no water seal is employM in conjunction with the safety or relief valves utilized at CR-3.

l Therefore, it can be concluded that the test conditions encompass and exceed the design conditions for Crystal River Unit 3.

The specific tests and detailed data sheets which have been or are to be performed on safety and relief valves applicable to Crystal River Unit 3 are presented in Reference 1, Sections 3.2 and 4.1, respectively.

Further, EPRI Report NP-80-13LD (Reference 2), presents further data on safety and relief valve operability and reliability under steam and/or ,

water conditions as it relates to the Crystal River Unit 3 transient of '

February 26, 1980, and subsequent testing and examination of the valves. By this reference, the above mentioned report is incorporated as part of this submittal and further justifies the adequacy of the safety and relief valves utilized at Crystal River Unit 3.

i Ccok(Report)DN108-3

IV. EVALUATION OF DISCHARGE PIPING AND EFFECT ON VALVE OPERABILITY Pursuant to the expansion of the recommendations of NUREG 0578 and NUREG 0737, EPRI is generating substantial data to be utilized in determining the effect of the discharge piping on valve operation. However, the scope and completion schedule of the ensuing evaluation effort is un-known. Nevertheless, based on the results of the February 26, 1980, transient at Crystal River Unit 3, it can be shown and concluded that the discharge piping had no adverse effect on valve operation with re-gard to Crystal River Unit 3 (as dacur-a+ed in Reference 2). As well, evaluations performed subsequent to t aforementioned transient show that no degradation of the integrity of the discharge piping resulted due to the actuation of the safety or relief valves. These evaluations have been submitted to the U.S. Nuclear Regulatory Commission by Florida Power Corporation in documents dated June 25, 1980, and July 17, 1980.

These submittals (References 3 and 4) hereby become an integral part of this document.

l t

I i C, ' Report)DN108-3 l

V. CONCLUSIONS Based on the results of the testing performed under the auspices of the EPRI PWR Safety and Relief Valve Test Program (Reference 1), the examin-ation and evaluation of the Crystal River Unit 3 safety and relief valves following the transient of February 26,1980 (Reference 2), the experience gained from the aforementioned transient concerning the Crystal River Unit 3 specific discharge piping effects on valve opera-bility, and the evaluation of the discharge piping integrity (References 3 and 4), it is concluded that by this submittal Florida Power Corpora-tion has satisfactorily addressed all applicable concerns recommended by NUREG 0578 and NUREG 0737. However, Florida Power Corporation remains committed to follow the EPRI program to its conclusion in order to insure that any future findings which may affect our conclusions are immediately identified and dealt with in a timely manner, and that the U.S. Nuclear Regulatory Commission is provided specific evaluations and data as it relates to Crystal River Unit 3 based on future EPRI find-ings.

I i

l Cook (Report)DN108-3 l

l l

l

o .

VI. REFERENCES

1. "EPRI/PWR Safety and Relief Valve Test Program - interim Data Re-port", July 1,1981.

2. EPRI NP-80-13LD, " Examination and Test of Crystal River Unit No. 3 Power Operated Relief and Safety Valves, Interim Report", December 1980.

3. Mr. R. M. Bright (FPC) to Mr. R. W. Reid (DOR /NRC) " Crystal River Unit No. 3, Docket No. 50-302, Operating License No. DPR-72, NRC letter dated May 2,1980 Requesting Information Concerning Pressur-izer Safety Valves", June 25, 1980.

4. Dr. P. Y. Baynard (FPC) to Mr. R. W. Reid (D0R/NRC), " Crystal River Unit 3, Docket No. 50-302, Operating License No. DPR-72, NRC letter dated May 2, 1980 Requesting Information Concerning Pressurizer Safety Valves", July 17, 1980.

Cook (Report)DN108-3 l

.)