ML20010D579
| ML20010D579 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Calvert Cliffs, Oconee, Palisades, Saint Lucie, Crystal River, Midland, Fort Calhoun, Crane  |
| Issue date: | 08/06/1981 |
| From: | Knight J Office of Nuclear Reactor Regulation |
| To: | Novak T, Tedesco R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19291D364 | List: |
| References | |
| NUDOCS 8108280274 | |
| Download: ML20010D579 (6) | |
Text
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h AUG 61981 Mst MEMORANDtfM FOR: Robert L. Tedesco, Assistand Director h
for Licensing e'
Division of Licensing
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2 Thomas H. Tiovak, Assistant Directcr b
for Operating Reactors Division of Licensigg
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FROM:
James P. t'nj%
4 for Compon6nts and Structures Engineering Division of Engineering i
SUBJECT:
REPORTING OF UNSATISFACTORY EPRI/P11R TEST RESULTS FOR DRESSER MODEL 31739A AND CROSBY MODEL 3K6 SAFETY WI1/E TheattachedmemorandAfromEPRIfortheweeksofJuly6, July.13and July 18 discuss the results of steam and water tests performed at Hyle.
Horco on the Masonellan and Copes Vulcan (17-4 Pil plug.and cage) PO D 's.
l These PORV's passed the EPRI " screening criteria" for all of the tests.
Both Safety Valves, however failedA. screening criteria in one or more tests as described.in the memorandesa. For each " failure", the applicable criterion is as stated in the.menorandum. Note that all.of these tests were.perfomed on steam with a short inlet piping configuration. These l
two valves have not been tested as yet.with the long loop seal inlet pining configuration that is nomally used on Westinghouse plants.
It.is our understanding that the Licensees and. Construction Pemit iloiders that utilize or plantto utilize these safety valves and the USSS vendor have been notified of these test results and have the. responsibility for assessingthesafetysignificanceoftheobrervedvzVtbehaviorfortheir
- plants, i
CWinfomation from EPRI indicates that the Dresser 31739A Safety Valve is being used or will be used on the following Plants:
Calbert Cliffs 1 and 2 Crystal River 3 Palisades THI - 1 Midland I and 2 fiillstone 2 Oconee 1, 2 and 3 The Crosby 3K6 is being used or will be used on the following Plants:
St. Lucie 1 and 2 f
Fort Calhoun 1 1)'
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OFFICIAL RECORD COPY
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Robert L. Tedesco "
i Although the specific safety significance of these test results is still being evaluated, this infonnation may be selevant for Board notification.
If a decision is made to forward this infonnation to one or more Boards, I
we recommend that a copy of the July 22, 1981 memorandum from Frank Cherny j
to Robert J. Bosnak be forwarded to the Board also. A copy of the memorandum j
was previously distributed to you.
It contains the minutes of the July 17, 1981 meeting between the staff and EPRI and the PWR Owners Group at which l
the status of all of the Safety Valve and PORY testing in the EPRI program l
was discussed.
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James P. Knight, Assistant Director for Components & Structures Engineering Division of Engineering cc:
R. Vollmer F. Cherny E. Hemminger H. Gregg R. LaGrange Z. Rosztoczy R. Kiessel E. Jordan i
E. Brown l
D. Chaney l
R. Clark S. Yarga W. Johnston l
R. Bosnak l
D. Dilanni I
DISTRIBUTION:
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i ELECTRIC POWER RESEARCH INSTITUTE l
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July 24,1931 l
TO:
DISTE15LT10N C_
FOM:
John J. Carey j
i SUEJECT:
S/RV TEST ACTIVITIES Tne EPP,1/PWR Safety and Relief Valve Test Program testing activities for l
the period of July 15-24 were as follows:
WLE I
4 DJring the pariod Saturday, July 18 throu::5 Friday. July 24. eicht tests were performed on the Copes Vulcan relief valve utilizing the 17-4 P.H.
Plug end Cege.
The tests were perforced under steam, prelcad, water, steem j
to water transition and water seal sin.nlation conditions.
During all tests the valve opened and closed on demand.
The valve was disassembled and inspe:.ted and no darsge was observed-that would affect future valve per-forma nce.
The next valve to be tested is the Copes Vulcan relief valve utilizing the i
316 w/ stellite plug.
l COMSU3 TION Et;GIhEERING Six tests were perfomed on the~. Crosby 3K6 safety valve this week.
Three high ramprate, hi~gh beckpressure, stean tests were performed on l
Tuesday.
l l
she first test was performed with an adjusted ring setting to improve valve blowdown.
The velve opened at 'a pressure within + 3% of the valve design set pressure. A stem position greater then 103% of rated lift was achieved at a pressure of 6% above the valve design' set pressure.
During the test the valve started to oscillate (chatter), subsequently the test was terminated. Blowdown date wes not obtained.
Feak back pressure was 865 psia.
The second test was performed with an intermediate ring setting and a l
slightly reduced backpressure. All EPRI screening criteria were satisfied.
Feak baci. pressure was 715 psia.
l The third test was performed with a third ring setting adjustment.
Due l
to instrumentation problems encountered during the test. valve stem posi-tion was not recorded. The test tlas repeated on Wednesday, i
l HsMinusilers 3412 Hatview Avenue, Pou Omce Box 10412. Paio Alto. CA 9G03 (415) 655 2033 Memptwo O)M.y thD3 Ws.actwtetts kemor. Nat.sn;tts 700. %shinaron. OC 20936 (202) t:12-9222 mm, --mm _ - - - -...
l S/RV TEST ACTIVITIES 1
Fage 2 1
F:;r it.e reacst test the valva cycled three tires.
For the first cy:le, j
all EFF.I screening criteria were satisfied.
Fa t Lecipressure was 703 psia.
For the second cycle, the valve opened at a pressure of 3.3%
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belcw the valve design set pressure which is below the C;RI crening pressure criterion.
The valve closed at a pressure within 10% of the valve design set pressure. The date for the third cycle has not yet been redated, i
The second test perforned on Wednesday, was a high ramp rate. low back pressure, steam test hith the intentediate ring tetting adjustment.
This rir.g setting was the sate es that used for the second test per-formed on Tuesday.
This ring setting was selected for the remainder of the tests on the Crosby 3h6 safety valve.
For this test the EPRI screening criteria were satisfied.
Feak backpressure was 233 psia.
On Friday, a steam to water transition, low flow test was performed.
For this test the valve cycled two times.
For the first cycle the EFRI screening criterion were satisfied.
For the second cycle the valve opened at a pressure of 4.7%, below the valve design set pressure which is below the EPRI blowdown pressure criterion.
The valve closed at a pressure within 10% of the valve design set pressure.
JJC/WJ5/mw DISTRIBUTION D. Hoffmen
- Tele:cpy # 517 768-0134 0, Sc:tt
- Telecopy # 201-430-573 -
4. Cherny (NRC)
- Telecopy f 3D1-C92-4934 Parefax set at 6 J. Rosenberger
- Telecopy # 305-552-4192 (Florida Power & Light)
T. McIvor
- Tele:Opy # 402-535-4455 (Oraha Fablic Fower District)
T."Vanderventer (philadelphia Electric Co.)
K. Beskin, Cheircran - CE Dwners Group B. Gill, Thairman - EM Owners Group 4
R. Jurgensen, Chaire.an '- W Owners Group
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Te:hnical Contacts - Participating Utilities W. E. Le uenstein
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J. J. Taylor f
F. J. Arrotta G. Williattson
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Memorandum July 17,1981 TO:
DISTRIBUTION John J. Carey \\ O # '
ROM:
SUEJECT:
S/fa TEST ACTR TIES The EPRI/PUR Safety and Relief Valve Test Frogrn testing activities for the period of July 13-17 oere as follows:
WYLE During the period from Friday, July 10 through Wednesday, July 16 testing was performed on the Masoneilan relief valve. Tne tests were performed under steam, preload, water, transition and water seal simulation conditions.
One additional The full pressure, 33DeF water test and tc repeat tests were also performed.
two repeat tests had a sli htly increased air supply pressure to the air 5
actuator to irprove valve opening tire. - A totsi of eleven tests were performed.
For all tests the valves opened and closed on decend.
Tne valve was dis-asserbied and inspEtted by :Se Mesoneilan valve representative.
No damage was observed that would affect future valve performance.
Tne cage to body gasket had washed out during testing.
The Copes Vulven relief valve utilizing the 17 C ph plug and cage was installed today. Testing is scheduled to start tor.orrow, July 18.
C3"SU5 TION ENGINEERIkG This During this week four tests were performed on the Crosby 3KE safety valve.
The first three tests were low valve has a design set pressure of 2500 psia.
ramp rate, short duration, high backpressure, steam tests.
Due to cerputer and instrumentation problems encountered during the first two tests, all c:ta was not recorded.
The ' third test was performed on Thursday, July 16.
For this test, the valve A mexirum opened at a pressure within i 3% of the valve design set pressure.
sten position of 98% of rated lif t was achieved.
Fated flow was achieved.*
The valve closed at a pressure of 2245 psia, which is.2% belce the EPRI blow-down pressure criterion of 2250 psia.
Peak backpressure for this test was 650 psia.
On Friday, July 17 the fourth test on the Crosby 3K6 safety valve was performed.
The valve This test was a high ramp rate, high backpressure, steam test.
A riaximum opened at a pressure within + 3% of the valve desien set pressure.
stem position of 9M of rateli lift oss achieved at a pressure of 6% above the
~
Rated flow was achieved.* The valve closed at a valve design set pressure.
pressure of 2225 psia, which is 1% below the EPRI blowdown pressure criterion of 2250 psia.
Peak backpressure for this test was 620 psia.
The next test on the Crosby 3K6 safety valve is scheduied for Handey, July 20.
- Based on preliminary venturi flow data.
t' t
Memorandum-1.'t
[2 July 10,1981 i
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TO:
DISTRIBUTION.
]
FROM:
John J. Carey'
's
SUBJECT:
S/RV TEST ACTIV IES The EFRI/PWR Safety and Relief Valve Test Frogram test,ing activities for the period of J ly 6-10 Were as fo11cus:
WYLE Installation of the !bseneila'n relief valve took piece this week.
Testing j
was deleyed due to facility boiler problems encountered during systen heatup.
Tie problers have been resolved.
l scheduled to start today.
~
Testing of the Hasor.eilan relief valve is i
COM30STION ENGINEERING l~
On tbnday, July 6, a high ramp rate, high back pressure, steam test was per-formed on the Dresser 31730A safety. valve.
For this test the upper ring controlling the.effect of back pressure on valve' perforcance was adjusted.
The valve opened at a pres:iure within + 3% of the valve desigr. set pressure.
A caximum sten position of 111't of rated lift was echieved at 6% of the valve design set pressure.
Rated flow &las achieved.* The valve closed at a pressure 2245 psig, which is below the EFRI blewdown pressure of 2250 psig, j
The EPRI screening criterion was not tr.et.
I The Dresser 31739A safety valve was removed from the test stand on July 6.
l The Crosby 3KS safety valve is presently being installed for testing. -
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