ML18139C010
| ML18139C010 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 08/31/1982 |
| From: | Grayson R, Kelly R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML18139C009 | List: |
| References | |
| TASK-2.D.1, TASK-TM MDQ-PVE-671, NUDOCS 8209080371 | |
| Download: ML18139C010 (12) | |
Text
.. MDQ-PVE.:.671
- r~ e e PWR SAFETY AND RELIEF VALVE TEST PROGRAM, PORV BLOCK VALVE ADEQUACY REPORT FOR VIRGINIA ELECTRIC POWER COMPANY NORTH ANNA UNIT l AND UNIT 2 AUGUST 1982 Approved By:__,_~
___{;__....;......,~.......--~-~~**.-"~'-*----------~
R. E* ./irff-'=J Wes~inghouse Electric Corporation Nuclear Energy Systems P.O. Box 355 Pittsburgh, PA 15230 8209080371 820901 PDR ADOCK 05000280 p PDR L.__ _ _ .
l MDQ-PVE-671
1.0 INTRODUCTION
e e NUREG-0737, Item II.D.l.B requires PWR utilities demonstrate block valves function properly over expected op~rating and accident conditions. This demonstration is to be supported by test data.
During a meeting between the NRC staff and utility representatives on July 17, 1981, agreement was reached regarding resolution of the above requirement. Details of the utility position on block valve testing is contained in Reference 1. . .
In response to NUREG-0737, Item II.D.l.B, Reference 2 transmitted to the NRC EPRI PWR Safety and Relief Valve Test Program, PWR Safety and Relief 11 Valve Test Program, PORV Block Valve Information P~ckage", May 1982 (Reference 3).
- Included in this submittal was:
- A description of block valves used in or planned for use in PWR plants.
t
- An EPRI report entitled "EPRI/Marshall Electric Motor Operated Valve (Block Valve) Jnterim Test Data Report," May 31, 1982. *
- A Westinghouse report entitled "EPRI Summary Report: Westinghouse Gate Valve Closure Testing Program," March 31, 1982.
Reference 2 also states that PWR utilities.,, belitYe sufficient evidence*
(supported by test data) is available to demonstrate block valve "operability".
Response to the N~REG requirement was to be fulfilled by submittal of the above mentioned document package and a separate plant-specific evaluation of safety and relief valve operability. ,
This document provides the plant-specific response and evaluation of the Block Valve Test program for Virgi.nia Electric Power Company's North Anna Unit l and Unit 2.
2.0 BLOCK VALVE DESIGN INFORMATION The block valves installed at North Anna Units l and 2 are Velan model*#
Bl0-354B-13MS m6tor operated gate valves (described in Table 2-1) and Westinghouse model 3GM88 motor operated gate valve (described in Table 2-2).
During the EPRI Test program tests were conducted on a Velan model B10-
. 3054B-13MS block valve and a Westinghouse model 3GM88 block valve at the Marshall test facility. Results of those tests are detailed in Reference 3.
For comparison a description of the Velan and Westinghouse test valves is provided in Table 2-3 and 2-4. As can be seen, the North Anna valves tested by EPRI aresi~ilar to -the block valves installed at North Anna.
e e MDQ-PVE-671 TABLE 2-1 VELAN PORV BLOCK VALVE DESCRIPTION
- Velan Information Manufacturer ***.
- Velan Engineering Companies Description.
- Motor Operated Bolted Bonnet Gate Valve Quantity . .
- 3 (Total)
Model . . * . . .. Bl0-354B-13MS Drawing No. .*** 88418-3 Valve Operator Information Manufacturer .* .**.*.*.. Limitorque Description *** . .* . .* Motorized Valve Operator Mode 1. . . ****.**.. SMB-00-15 Voltage, Volts . * * * .
- 460 Speed * * . . . . . . . * . . . . 10 sec. (open or closed) .
RPM . . . . * * * . 1800
e e MDQ-PVE-Q71 TABLE 2-2 WESTINGHOUSE PORV BLOCK VALVE DESCRIPTION Valve Information Manufacturer
- Westinghouse Electric Corporation Description. Motor Operated Gate Valve Quantity **
- 1 Model. . . . . .
- 3GM88 Drawing No *. *** 115E075 Valve Operator Information Manufacturer. . . *
- Limitorque Description . . * * . Motorized Valve Operator Model . . * . . . . SB-Oo.:15 Voltage, Volts *
- 460 Speed. *
- 10 sec.
RPM. .
- 3600
.. . -~ . ... .
e MDQ-PVE-671 TABLE 2-3 _
TEST VALVE DESCRIPTION, TEST SERIES M-VEl*
General Valve Information Manufacturer . * * * * *
- Velan Engineering Companies Description *. * * * * * * * *
- Motor Operated Bolted Bonnet Gate Valve Model. . * .
Seri a1 No. . * * * . . . ***...**
Drawing. * * * . * * * * * * * . * .
- Bl0-3054B-13MS 765 88425/B General *valve Operator Information Manufacturer . * * * * *** Limitorque Description. * * * * * . Motorized Valve Operator Model. . * * * * * * * * * *** SMB-00-15 Serial No~ * * . * * * * * * * * * *
- 243402 Torque Switch Setting. * ! ** 1.7 Voltage * * * * * . * * . . _* * . * . . 460 RPM . . * * * * * * * * * . * * . * * .
- 1700
- Source: Reference 3
e e MDQ-PVE-671 TABLE 2-4 TEST VALVE DESCRIPTION, TEST SERIES M-WSl**
General Valve Information Manufacturer . . * . * * . . . . * * . Westinghouse Corporation Description. . . . . . . . .. Motor Operated Gate Valve Model * . * . * * * * . * . . MOD03000GM88FNB0DO (88 Series)
Serial No . . * . * .
- Drawing No *. * . 8374034 General Valve Operator Information -~
Manufacturer * * . . . . . . . *. Limitorque .
Description . * . * . * . . Motorized Valve Operator Model * . . * * . . * . . . * . SB-00-15 Serial Noo o o o o . o
- Torque Switch Setting.
- Voltage . * . * . . * . 575 RPM. . * .* * * * . '!I * . . 3600
- Not Supplied by the manufacturer
- Source: Reference 3
MDQ-PVE-671 e e 3.0
SUMMARY
OF BLOCK VALVE TEST RESULTS 3.1 Velan Block Valve Results of the Velan block valve tests are contained in Section 3.1 of Reference 3.
The evaluation tests were performed at the Marshall Steam Station test facility with the Copes-Vulcan PORV installed downstream of the Velan test valve. The Velan valve was cycled 21 times and the results of these tests are sununarized in Table 3.1-3 of reference 3.
Seat leakage, flow and stroke tests were conducted.
The test valve was cycled against full flow at 2340-2500 psi nominal line pressures. EMOV stroke times were reported between 9.7 and 9.9 seconds. No appreciable seat leakage was measured. The valve fully opened and closed on demand for each of the 21 test cycles.
Additional supplementary tests were conducted to evaluate valve operability with reduced operator torque. Results of these tests were summarized in Table 3.1-4 of reference 3. The valve fully opened and closed on demand for each of the supplementary test cycles.
- Following the testing program, the Velan test valve was disassembled and inspected. Very slight galling of the guides was observed but all other parts including seating surfaces were found to be in good condition. *
- 3.2 Westinghouse Block Valve Model 3GM88 Results of the Westinghouse 3GM88 Block Valve Tests are contained in Section 3.2 of reference 3.
The evaluation tests were conducted at Marshall Steam Station test facility with the Control Compo~ents International PORV mounted downstream of the Westinghouse test valve. The*valve was cycled 21 times and the results of these tests are summarized in Table 3.2-3 of reference 3.
Prior to initiation ~f the.evaluation tests, several* attempts were made to outfit the valve with a motor operator with 575 volt .capability as required by the Marshall test facility electric power supply.*
- Initially no 575 volt Limitorque operator was available so several*
Rotork operators, available at that time, were _tried. During ,these preliminary checkout.s, difficulty was encountered with closing the valve completely. Finally a 575 volt Limitorque SB-00-15 operator was made available and installed on the test valve.
On the initial evaluation test, considerable valve packing leakage was observed. The packing was tightened to stop the leakage. When the valve was cycled it remained 4% open. The torque switch setting was increased and the valve closed fully on the second attempt and throughout the remainder of the evaluation tests.
MDQ-PVE-671 e e
- The valve was cycled against full flow at 2280-2420 psi nominal line pressures. Stroke times were reported between 6.2 and 12.9 seconds. No appreciable seat leakage was measured. The valve fully opened and closed for 20 of the 21 evaluation cycles. As stated above, the valve closed to within 4% of closure for the first cycle.
S_upplemental test results are surrunarized in table 3.2-4 of reference 3 and detail the calibration and checkout activities that were carried out during the period of June *27, 1980, to.August 11, 1980, as well as two additional cycles which* occurred after the*
evaluation tests.
The test valve was inspected after the evaluation tests and all internal parts were in good condition.
A subsequent examination made after all testing showed the wedge guides evidenced some galling but all other parts were in good condition.
During the testing at Marshall, the stem thrust required to close the valve was measured _using axial-type strain gages. The resulting forces were cpnsiderably higher than .. expected. When subsequent closure problems occurred in Spain a series of tests and analyses were conducted by Westinghouse to determine the caus~ of the higher than expected closing loads. A report of this testing and analysis is contained in reference 3.
This report concludes the closure problems encountered were the result of under-predicting the stem thrust required to close the valve against high differential pressures. The standard closing load equation used by Westinghouse had to be modified based on test results.
- Several of the other.valves in the EPRI program closed quite success-fully even though their actuators were most likely sized using the 0.3 valve factor. This can be explained by the difference in operator sizing philosophy between Westinghouse and most other valve companies.
- Most other companies al low Limitorque to perform the.ir operator sizing.
The standard Limitorque technique has sufficient margin built into it at other points of the sizing calculation that the final operator is adequate and most valves would close at the higher actual loads~
4.0 CONCLUSION
S The Velan and Westinghouse valves tested at the Marshall Steam Station as part of the EPRI Safety and Relief Valve test program are similiar in design to the block valves installed at North Anna Unit land Unit 2 and these valves successfully completed the evaluation and supplementary test program, fully opening and closing on demand.
I' ..., "
- e e MDQ-PVE-671 Furthermore, the Westinghouse model 3GM88 block valve installed at North Anna has been modified by Westinghouse to provide sufficient closing thrust as determined in the Westinghouse test program.
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,. VIRGINIA 23261 R.H.LEASBURG September 'l, 1982 VxcE PRESIDENT NUCLEAR Q;pERATIONS Mr. Harold R. Denton, Director Serial No. 506 Office of Nuclear Reactor Regulation NO/DJF:ms Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:
NUREG 0612 - CONTROL OF HEAVY LOADS SURRY POWER STATION UNIT NOS. 1 AND 2 On August 12, 1982 a conference call was held between Vepco, the NRC and Franklin Research Center personnel. The following information is provided concerning areas requiring further action as a result of the conclusion and recommendations shown in the draft Technical Evaluation Report fot Control of Heavy Loads at Surry Power Station a~d the August 12, 1982 conference call.
TER 2 .l. 2 SAFE LOAD PATHS f GUIDELINE, NUREG-0612, SEC. 5 .1.1 (1)}
Comment:
It was stated by the NRC that in order for Surry to fully comply with the guidelines, the licensee should clarify the procedure for handling deviations from safe load paths.
Response
Vepco stated that this information is presently available to the NRC and that it could be found in Section 5 of Vepco's Nuclear Power Station Quality Assurance Manual and in Section 6 of the Surry Power Station Technical Specifications. The procedure for deviations to procedures requires review by station supervisory personnel with a followup review by the Station Nuclear Safety and Operating Comm,ittee.
TER 2.1.4 CRANE OPERATOR TRAINING {GUIDELINE 1, NUREG-0612, SEC. 5.1.1(3)}
Comment:
Under Section b. Evaluation of 2 .1. 4 it was stated that the licensee should ensure that a mechanism is in place to provide future crane operator training that meets the intent of ANSI B30.2-1976, Chapter 2-3.
-~ * -
- 73 820901
VIRGINIA ELECTRIC AND POWER COMPANY TO e
2
Response
Surry Power Station presently has procedures for the initial training of crane operators. There are presently no provisions for retraining or future operator training beyond the initial training of the personnel.
By the next refueling outage at Surry Power Station procedures will be developed to provide future crane operator training that meets the intent of ANSI B-30.2-1976, Chapter 2-3.
TER 2. 1.5 SPECIAL LIFTiNG DEVICES {GUIDELINE 4, NUREG-0612, SEC. 5. L 1(4)}
Comment:
The NRC stated that they would like the schedule dates that Vepco has for the completion of the Westinghouse analyses of special lifting devices used at Surry Power Station.
Response
The dates for completion of the analyses as provided by Westinghouse and submittal to Vepco are as follows:
- January 1, 1983 - Preliminary Stress Report
- February 1, 1983 - Preliminary Evaluation
- March 1, 1983 - Final Report After internal review Vepco would submit the results of this review by no later than March 31, 1983.
TER 2 .1. 6 LIFTING DEVICES (NOT SPECIALLY DESIGNED) {GUIDELINE 5, NUREG-0612 SEC. 5. 1. 1 (5) J Comment:
The NRC stated that an evaluation must be performed to determine the significance of dynamic loads on the slings used for lifting heavy loads. If there are significant dynamic loads slings shall be marked to indicate. which slings are restricted in use to only certain cranes.
Response
Vepco will evaluate the significance of dynamic loads on the slings used and provide the NRC with the information by October 15, 1982. If the results of the evaluation indicate the necessity to mark the slings, they will be marked prior to their next scheduled use.
VIRGINIA ELECTRIC AND POWER COMPANY TO e
3 TER 2.2.3 SPECIAL REVIEW FOR HEAVY LOADS HANDLED OVER THE CORE {INTERIM PROTECTION MEASURE 6, NUREG-0612, SEC. 5.3(6)}
Comment:
The NRC stated that the licensee should verify that the one-time visual inspections of load bearing components of cranes, slings, and special lifting devices to identify flaws or deficiencies that could lead to a component failure have been performed and the appropriate repairs/replac-ments have been completed.
Response
Surry Power Station Preventative Maintenance Procedure MMP-P-CR-015 for periodic inspections of containment cranes and lifting equipment satisfies this requirement.
Per this procedure cranes, reactor head and internals lifting rigs are inspected prior to each refueling and at each containment maintenance period if they are to be used and have been idle for a period of more than six (6) months or the last inspection has been over one (1) year.
The reactor coolant pump motor lifting rig and wire rope slings are inspected prior to each refueling and at each containment maintenance period if they are to be used and the last inspection has been over one (1) month.
The one time inspectibn required will be performed prior to the next refueling in accordance with :the above procedure.
If you have any questions or require further clarification concerning the above subjects, please advise.
v7ii[J:;
R.H. Leasburg cc: Mr. James P. O'Reilly, Regional Administrator Region II Atlanta, Georgia 30303