ML20198E845
| ML20198E845 | |
| Person / Time | |
|---|---|
| Issue date: | 12/20/1985 |
| From: | Cherny F Office of Nuclear Reactor Regulation |
| To: | Bosnak R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20151L176 | List: |
| References | |
| FOIA-86-266 NUDOCS 8605280296 | |
| Download: ML20198E845 (7) | |
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j,2<ic,y M g,, % UNITED STATES y ', ) g NUCLEAR REGULATORY COMMISSION g ,,
WASHINGTON, D. C. 20555
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pg[k1b MEMORANDUM FOR: Robert J. Bosnak, Chief Engineering Issues Branch Division of Safety Review and Cversight FROM: Frank C. Cherny, Section Leader Section B Engineering Issues Branch
SUBJECT:
TRIP REPORT - MEETING OF ASME SECTION III SUBGROUP ON PRESSURE RELIEF, DECEMBER 10, 1985 The refrenced n;eeting was held at the United Engineering Center in New Ycrk City. A syncpsis of major items of interest to NRC is contained in the attachment to this men:orandum. Infomaticr cn all the agenda items is available in my file.
i.i . !Ab Frack C. Cherny, Section Leader Section B Engineering Issues Branch
Attachment:
As stated '
cc: T. Speis J. Richardson W. Campbell W. Norris G. Millman H. Gregg, RI K. Kniel
- 8. Sheron G. Hanr.er 4
8605280296 860508 PDR FOIA MURPHY 86-266 PDR g I
- 1) Should the Code perniit Safety Valves to be used for liquid service?
This ~qVe's'tlon was rats'eV Fy'We VrTtWr" FeVaVsY'o'f'tWe'Va't'a " twat has become available the last 3-4 yrs., both frcm EPRI and some operating reactor events, indicating poor performance for this . type of valve en liquid. -Those present including the Orcsser representative, appeared to favor continuation of the existing code requirements which sin: ply do not state that safety valves are acceptable for liquid service. This iten.
was " tabled" because the Crosby representative was not at the neeting.
There does not appear to be an ob'vious answer. The existing Code words were written before the Full Size Cerronstration of Functinn Test was included. Theoretically, at least, it would seem that if a safety valve could pass the demonstration cf function test on liquid it should be acceptable for that service.
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.@.5,5,(s.1 The writer discussed ongoing activities at NRC related to concerns over inadequate ring adjustments which has resulted in instances of MSSVs failing to achieve less than rated lift in recent testing. To address this concern for future MSSV designs, the writer proposed .that a requirement be added to NC-7000 that each CL.2 MSSV production valve be full flow tested by the manufacturer prior to shipment. There were no stated objections from the SGPR members present. -It is kncwn that Crosby has the capability to perform such tests. The Target Rock representative stated that T/R will have in the near future. The Dresser representative stated for a little higher purchase price, Dresser could have the testing done at Wyle Labcratory in Huntsviile, Alabama.
The writer was assigne'd to draft specific words for the test proposal for the March '86 SGPR meeting. ,
- 8) French PWR Dual Safety, Va,1y,e,,C,onf,i,guration A couple of neetings ago, the writer discussed with SGPR the dual in series Sebim Pilot Operated Safety Valve configuration being used on scrre PWRs in France. The SGPR reaction at that tine had been that the configuration does not neet the Code because the Code does not address dual valve installation requirements. As part of the NS-7000 re-review, the SGPR focussed on para. NB-7141(f) which was written to permit case by case justification of long inlet piping configurations for safety valves, safety relief valves, and relief valves. The SGPR members were generally of the opinion that these words may provide an unintentional " loophole" in the existing Code for justifying on a case by case basis the acceptability of a dual valve configuration. However, it was concluded that as a future activity SGPR would add sont specific requiren+nts into NS-7000 to address-dual in series configurations analogous to the requirements for safety valves used in combination with rupture disk devices.
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' NORTH ANNA, UNIT 2 - FAILURE OF MULTIPLE MAIN STEAM SAFETY RELIEF ENGLE, NRR) p PROBLEM: y SURVEILLANCE TESTING IDENTIFIED 8 0F 15 MAIN STEAM g C SAFETY VALVES FAILED TEST ON-SITE VERSUS OFF-SITE TEST METHODS MAY CAUSE DISCR ANCIES IN THE CALIBRATION AND DETERMINATION OF VALVE SETPOINTS SIGNIFICANCE:
LOSS OF MAIN STEAM SYSTEM OVERPRESSURE PROTECTION P0TENTIAL GENERIC APPLICABILITY
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DISCUSSION:
- IN MODE 4, MAIN STEAM CODE SAFETY VALVES TESTED WITH AIR PNEUMATIC DEVICE AND AT HOT CONDITION IN MAIN STE LINES TEST RESULTS IDENTIFIED 8 OUT OF 15' VALVES FAILED l TO DURING TEST (BEYOND 1% TOLERANCE) '
VALVES BEING SENT TO OFF-SITE TEST FACILITY FOR FURTH TESTING i
FOLLOW-UP:
LICENSEE ACTIONS l SENDING 10 VALVES TO AN INDEPENDENT TEST FACILITY FO DETERMINATION OF AS-FOUND SETPOINT AND CALIBRATION j
8 VALVES WHICH FAILED TO LIFT WITH PNEUMATIC ASSIST 1 VALVE WHICH LIFTED PROPERLY AFTER ADJUSTMENT 1 VALVE WHICH WAS FOUND TO BE ACCEPTABLE.AS-IS EVALUATING SAFETY CONSEQUENCES AND IMPLICATION NRC REGION II FOLLOWING UP DN OFFSITE TESTING OF VALVE
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- i i NORTH ANNA UNIT 2 I
MAIN STEAM SAFETY VALVES PNEUMATIC ASSIST TEST METHOD RECOMMENDED BY VALVE MANUFACTURER FOR IN-SI DEVICE UTILIZES AN AIR CYLINDER AND PISTON IS CLAMPED TO THE VALVE STEM AND WHICH C SPRING FORCE WHEN AIR IS SUPPLIED LIMITED BY STEAM GENERATOR PRESSURE AN LIFT PRESSURES LESS THAN ABOUT 1160 PSIG TEST METHODS USED DURING PREVIOUS OUTAGES ~
UNIT 2 UNIT 1 PNEUMATIC ASSIST PNEUMATIC ASSIST MOST RECENT REFUELING OUTAGE l-FULL STEAM PRESSURE PNEUMATIC ASSIST PREVIOUS REFUELING OUTAGE AT INDEPENDENT TEST FACILITY .
PNEUMATIC ASSIST PNEUMATIC ASSIST ALL OTHER OUTAGE T
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NORTH ANNA UNIT 2 MAIN STEAM SAFETY VALVES 1986 TEST RESULTS AS-FOUND SETP0 INT VALVE 1109 PSIG 1085 PSIG 201A " 1133 1149' B -
C -
1096 1095 i 202A "
1156' B - 1147' C 1124 1110 203A a .
1125 B a 1131 C 1127 -
1120 204A ~ 1159' l B " 1149' C 1161*
1135 205A " 1160*
B " 1149' C .
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This item was placed on the February 985 agenda for
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- ion III and was withdrawn f owing adverse commen . Trank Cherny cam up with new language that may be acc table to S III Subcommittee. This item was transmitte to ection III for action. Action is limited to NB ' 00. Section III approved this item without a gative vots The Item passed the hhin ;
6cmmi ee at the February eeting.
NP-1-85 Review of NX-7000 Paragraphs for learity and Uniformity w
The SGPR continued with the review of the .X-7000 paragraphs to clearify intent and maintain un ormity to the extent possible, for all classes. The vie will be continued at the next meeting.
NP-1~86 Production Testing of. Class 2 Main Steam Safety Valves-NC-7512.1 Frank Cherny passed out a proposed draft fo,r Class 2 (see Attachment A). Fr'a nk Cherny will pass this item on to Section III cecretary.
1 NP-2-86 Code Interpretation For Replaceme,wf of Parts l l
Dick Cedel passed out an nquiry dealing with the eplacement of press e retarning parts for pressure rel f valves, e subgroup reviewed the questions and provide gui nee. The inquiry will be submitted to the Sect y of the Main Committee (see Attachment E3) .
NP-3-86 Provisions When Stop Valves Are Used in Conjunction
. With a Pressure Relief Device 4 .
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- ATTACHMENT "A" ( }
,rECTION NC 7400-NC 7513.2 .
die cuxiliary loading force which augments the '
e exerted by the valve spring is automatically -
- onded a a pressure not greater than the set * (a) Safety valves shall be constructed l pessure of the valve. and adjusted to operate without
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Safety Valve Operating Requirements 8ta Ped capacity at a pressure not l N G7512 '
NG7512.1 Antlehattering and Uft Requirementsj greater than 3* above their set (fafety vaises shall be cor.structed to operate without pressutes.
I chattering and to attain rated lill at a pressure not cater 'han 3% above their set pressures.
NG7512.2 Openina Pressere Tolersace (b) For valves used for main steam
(?) The opening pressure tolerance plus or minus service, conformance with (a) shall shall not exceed the following: 2 psi for pressures up to and including 70 psi,3% for pressures over 70 psi to be established for each produetion 300 psi,10 psi for pressures over 300 psi to 1000 psi, valve by testing on steam at the and l% for pressures over 1000 psi.
stamped set pressure. The tese (b) Conformance with the requirements of(a) above
'shall be established for each production valve by test.
g shall eake ineo account valve Steam valves shall be tested on steam.
I discharge piping back pressure as NG7512.3 Blowdown Requirements. Safety valves shall be adjusted to close after blowing down to a 'specified in the valve Design pressure not lower than that specifed in the valve Specification.
j iuma shan tac deter-Design Speci5 cation. e '
~ ed oy test or y proration from the Certifica older's blowdown test data. (b) For valves used for main steam service, conformance with (a) shall N G7513 Safety RelleE and Relief Valve be established for each production Operating Requirements valve by testing on steam ae the Safety relief and relief valves shall be constructed to stamped set pressure. The test attain rated lift at a pressure not greater than 10%
above set pressure, except that for set pressures up to
- 25. psi, the overpressure shall not be greater than 2.5 discharge piping back pressure as P5'-8 specified in the valve Design NG7513.10pening Pressure Tolersace (2)'Ilie opening pressure tolerance plus or minus Specification.
from the set pressure of safety relief and relief valves shall not exceed 2 psi for pressures up to and including 70 pai and 3% for pressures above 70 psi. (c) For valves used for other than main (b) Conformance with the requirements of(s) above steam service, the adjustment shall shall be established for each production valve by test.
Steam valves shall be tested on steam, air or gas valves W dahd h a x ph i
on air or gas, and liquid valves on hqu,d. from the Certificate Holder's NG7513.2 Blowdown Requirements. Safety relief blow-down test data, and relief valves shall be adjusted to close after blowing down to a pressure not lower than that ^
spectaed in the valve Design Speciacation. The adjust. ~
ment shall be determined by test or by proration from the Cert 15cate Holder's blowdown test data.
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