ML20212C843
| ML20212C843 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/25/1987 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20212C847 | List: |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8703040014 | |
| Download: ML20212C843 (13) | |
Text
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TOLEGO EDISON Docket No. 50-346 JOEWILUAMS JR Serar Vce Ronders-Pennar (4191249 2300 License No. NPF-3 14'812d3 5223 Serial No. 1-705 February 25, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C.
20555 Gentlemen: is Toledo Edison's final response to the action items contained in IE Bulletin 85-03: Motor-Operated Valve Common Mode Failures During Plant Transients Due To Improper Switch Settings, dated November 15, 1985 (Log No. 1-1282). As indicated in our previous response dated May 15, 1986 (Serial No. 1-637), these action items were to be completed within 60 days after Davis-Besse Restart.
Very truly yours.
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JW DJSepif Attachments cc: DB-1 NRC Resident Inspector A. B. Davis, Acting Regional Administrator (2 copies) 0703040014 B70225 PDR ADOCK 05000346 yl e
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'HE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43052
Dockat Ns. 50-346 License No. NPF-3 Serial No. 1-705 ATOMIC ENERGY ACT OF 1954 SEC7 ION 182a SUBMITTAL IN RESPONSE FOR THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 FACILITY OPERATING LICENSE NO. NPF-3 This letter is submitted in conformance with the Atomic Energy Act of 1954 Section 182a in response to IE Bulletin 85-03 (Log No. 1-1282).
This deals with motor-operated valve common mode failures during plant transients due to improper switch settings.
By 244 ---- - j_
W1111ais Jr. f enfor Vice President, Nuclear Sworn to and subscribed before me this 25th day of February, 1987.
1YYLOL/1
/k Notary Public State of Ohio My Commission Expires
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Dock;t Ns. 50-346 License No. NPF-3 Serial No. 1-705 Action Item a. (Revised 1/19/87)
For motor-operated valves in the high pressure coolant injection / core spray emergency feedwater systens (RCIC for BWRs) that are required to be tested for operational readiness in accordance with 10CFR50.55a(g),
develop and implement a program to ensure that valve operator switches are selected, set and maintained properly. This should include the following components:
a.
Review and document the design basis for the operation of each valve. This documentation should include the maximum differential pressure expected during both opening and closing the valve for both normal and abnormal events to the extent that these valve operations and events are included in the existing, approved design basis, (i.e., the design basis documented in pertinent licensee submittal such as the FSAR analyses and fully-approved operating and emergency procedures, etc.).
When determining the maximum differential f
pressure, those single equipment failures and inadvertent equipment Y) operations (such as inadvertent valve closures or openings) that are within the plant design basis should be assumed.
Response to Action Item a.
The attached " Table of Results - IE Bulletin 85-03(a)", Revinion 1, was revised as a result of additional review of the design basis for the operation of each valve in the requested systems. This design review was performed in accordance with Nuclear Engineering Procedure NEP-092 Establish D/P Limits and Tests for Motor-Operated Valves (attached to Item d.).
The maximum differential pressure during both opening and cloning of each valve was determined consistent with the design basis events documented in the Updated Safety Analynis Report analyses and the Davis-Besse Nuclear Power Station normal and emergency operating procedures.
The revised values were incorporated into the program of Action Item b.
Docket No. 50-346 License No. NPF-3 Serial No. 1-705 Table of Results - IE Bulletin 85-03(a)
(Revision 1, 1/19/87)
Differential Pressure Values Experienced During Valve Operation Normal Normal Abnormal Abnormal Valve Event Event Event Event Component I.D.
Open Closed Open Closed Auxiliary Feedwater (AFW)
AFW Pump Turbine Inlet & Containment Isolation Valve (CIV)
MS 106 (DC Power) Main N/A N/A 1100 1100 MS 107 (AC) Main N/A N/A 1100 1100 MS 106A/107A (AC) Cross-Tie N/A N/A 1100 1100 AFW Pump Discharge Isolation AF 3869, 3871 (AC) Cross-Tie N/A N/A 910 171 AF 3872 (AC) Main N/A N/A 910 171 AF 3870 (DC) Main N/A N/A 910 171 AFW Pump Discharge Block AF 360 (DC) Main N/A N/A 0
400 AF 388 (AC) Main N/A N/A 0
400 AFW Pump Discharge CIV AF 599, 608 (AC) Main N/A N/A 1425 1425 Service Water Supply to AFW Pump Suction SW 1382, 1383 (AC) Main N/A N/A 146 146 i
liigh Pressure injection (HPI)
BWST Isolation for HPI Pump Suction Dil 7A, B (AC) Main 34 34 34 34 3
Containment Emergency Sump for HPI Pump Suction Dl! 9A B (AC) Main 30 30 36 36 IIPI Pump Discharge Isolation & CIV llP2A (AC) Main 1927 0
2200 1927 IIP 2C, 2D (AC) Main 1927 0
1927 1927 IIP 2B (AC) Hain 1927 0
1927 1927 IIPI Pump Minimum Recirculation & Non-Return Stop Check Valves llP 31, 32 (AC) 1875 1875 1875 1933
Dock;t N2. 50-346 License No. NPF-3 Serial No. 1-705 Action Item b.
Using the results from Item a., establish the correct switch settings.
This shall include a program to review and revise, as necessary, the methods for selecting and setting all switches (i.e., torque, torque bypass, position limit, overload) for each valve operation (opening and closing).
If the licensee determines a valve is inoperable, the licensee shall also make an appropriate justification for continued operation in accordance with the applicable Technical Specification.
Renponse to Action Item b.
Toledo Edison's program to establish, review and revise the settings for valve operator switches (torque, torque bypass, position limit) includes the results of Item a. and is covered by Nuclear Engineering Procedure NEP-091, Motor-Operated Valve Data Evaluation (attached to Item d.).
This program was completed on December 20, 1986.
l Dockst Na. 50-346 License No. NPF-3 Serial No. 1-705 Action Item c.
Individual valve settings shall be changed, as appropriate, to those established in Item b.
Whether the valve setting is changed or not, the valve will be demonstrated to be operable by testing the valve at the maximum differential pressure determined in Item a., with the exception that testing motor-operated valves under conditions simulating a break in the line containing the valve is not required. Otherwise, justification should be provided for any cases where testing with the maximum differen-tial pressure cannot practicably be performed. This justification should include the alternative to maximum differential pressure testing which will be used to verify the correct settings.
Each valve shall be stroke tested, to the extent practical, to verify that the settings defined in Item b. have been properly implemented even if testing with differential pressure cannot be performed.
Response to Item c.
Toledo Edison's program to implement change to valve switch settings is contained in Davis-Besse Maintenance Procedure MP-1410.32, Testing of Motor-Operated Valves Using MOVATS (attached to Item d.).
This procedure requires each valve to be stroke tented to verify proper valve and operator operation. Our program to demonstrate valve operability is based on H0 VATS testing of all nuclear safety-related valves followed by confirmatory testing of a representative sample of valves at their maximum differentini pressure. Not all valves will he differential pressure tested. Those valves tested were tested either by opening against a hydrostatically provided pressure or by opening / closing against process flow conditions, e.g. due to an operating pump. Tests are summarized in response to Item f. herein in Table titled, "85-03 Response Test Data."
Nuclear Engineering Procedure NEP-092 provides the program used to select the representative sample of valves to be tested to confirm the adequacy of corrective maintenance procedures. This procedure evaluates the practicability of specific valve differential pressure testing. This methodology has been reviewed with the NRC staff and submitted in our letter to Mr. Denton (Docket No. 50-346), Serial No. 1258, dated April 10, 1986. This program was conpleted prior to plant Restart.
Docket No. 50-346 License No. NPF-3 Serial No. 1-705 Action Item d.
Prepara or revise procedures to ensure that correct switch settings are determined and maintained throughout the life of the plant. Ensure that applicable industry recommendations are considered in the preparation of these procedures.
Response to Item d.
Toledo Edison's procedures to ensure correct switch settings are determined and maintained are already in place and consist of the following:
Nuclear Engineering Procedures NEP-091 Motor-Operated Valve Data Evaluation Procedure NEP-092 Establish D/P Limits and Testa for Motor-Operated Valves Davis-Besse Maintenance Procedures MP-1410.32 Testing of Motor-operated Valves using MOVATS MP-1411.04 Maintenance and Repair of Limitorque Valve Operators SMB-000 through SMB-00 MP-1411.05 Maintenance and Repair of Limitorque Valve Operators Types SMB-0 through SMB-4 MP-1411.06 Preventive Maintenance for Type SMB and SMC Limitorque Valve Operators MP-1411.07 Maintenance and Repair of Limitorque Valve Operators Type SMC-04 These procedures have previously been submitted as responses to questions in the Davis-Besse Course of Action (COA) and are attached for your convenience.
Dockat Ns. 50-346 License No. NPF-3 Serial'No. 1-705 4
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Action Item e.
Within 180 days of the date of this bulletin, submit a written report to the NRC that 1) reports the results of Item a. and 2) contains the program to accomplish Items b. through d.,
including a schedule for completion of these items.
l Response to Item e.
1 Toledo Edison's letter of May 15, 1986, included 1) the results of Item a.
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and 2) the program and schedule to accomplish Items b. through d.
These j
items are now completed as scheduled.
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Dock:t N3. 50-346 License No. NPF-3 Serial No. 1-705 Action Item f.
Provide a written report on completion of the above program. This report should provide 1) a verification of completion of the requested program,
- 2) a summary of the findings as to valve operability prior to any adjust-ments as a result of this bulletin, and 3) a summary of data in accordance with Table 2 Suggested Data Summary Format. The NRC staff intends to use this data to assist in the resolution of Generic Issue II.E.6.1.
This report shall be submitted to the NRC within 60 days of completion of the program. Tabic 2 abould be expanded, if appropriate, to include a summary of all data required to evaluate the response to this bulletin.
Response to Item f.
This report contains the requested Items 1, 2, and 3 for the bulletin.
Toledo Edison's program included not only the valves required by this document, but also all Limitorque Operated MOVs classified as safety-related or important to safety. The results for the entire program will be the subject of a separate submittal to avoid unnecessary reviews for tuis document. The summary of information as requested in Table 2 has been expanded and the information divided into three categories: Attach-ment 2. Valve Information; Attachment 3, Operator Information; and, Test Data.
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Dock 2t No. 50-346 Liccnra No. NPF-3 Snriel No. 1-705 ATTACllMENT 2 VALVE INFORMATION VR VE NUMBER VALVEFUNCTION MANUFACTURER VALVETYPE V RVE SIZE PMSSURE DESIGN KSIIN RATING M818 BASIS (CLASS)
B/P DIP 10 PEN)
.100E)
C3M MW PUMP DISCHARGE ROCK M P0 ELL COMPMY MTE 600 0
400 M3869 M W PUMP OllCH. CR088 ilE ISE M. POWELL COW M Y BATE 6M 910 171 G3070 MW PUMP MIN O!SCHARGE ISE.
M. P0utLL COWMY MTE 4
600 910 171 C3871 MW PUMP DISCH. CR0$$ TIE ISE M. PoufLL COWMY MTE H0 910 171 M3872 MWPUMPMAIN0!SCHARGEISOL.
M. P0utLL COMPMY MTE 6
6M 910 171 M388 M W PUMP DISCHARK K OCK M POWELL COMPANY BATE 6
6M 0
400 M599 MW PUMP DISCHARGE CIV VELM MTE H0 1425 1425 CH4 M W PUMP DISCHAR K CIV VELM BATE 6
6M 1425 1425 DH7A BWSTISOL.FORHPIPMP90C1.
M POELL COMPMY SATE 14 150 34 34
["79 BuliISOL.FORHPIPUMPSUCT.
M. POWELL COMPMY BATE 14 150 34 34 l
DN94
[MRO.lUMPSUCTFORltPIPUMP M. PoufLL COMPMY MTE 14 150 36 36 DN99 EERS.SUMPSUCf.FORHPlPUW M. P0utLL COMPMY BATE 14 150 36 36 C24 HP!PUMPOllCH.ISOL6CIV VELM K00E 2.5 1500 22M 1927 C28 HPIPUMPDISCH.ISOL.6Civ VELM K00E 2.5 15 #
0 1927 HP2C HPI PUMP DllCH ISOL. 6 CIV VELM K00E 2.5 1500 0
1927 HP20 HPlPUMPDilCH.ISOL.6CIV VELM K00E 2.5 1500 0
1927 C31 HPI PUMP MIN. RECIRC.
ROCKELL K00E l.3 1500 0
1933 C32 WI PUMP MIN. RECIRC.
ROCKWLL K00E I.5 1500 0
1933 Cl4 MW PUMP MAIN LEET M8 CIV VELM MTE 6
6M 1100 11 #
ClHA MW PUMP CRH8 TIE INLET 6 CIV VELM 6 ATE 6
H0 1100 llM C107 MW PUMP MAIN LEET M0 CIV VELM 8 ATE 6
600 1100 llM C1074 MW PUMP CROSS flE LEET 6 Civ VELM BATE 600 llM llM Cl382 SERVICE WATER SUP, TO M W PUMP JAMESIURYCORP BUTTERtLY 150 144.0 144.0 l
Cl383 SERVICE WATER SUP. TO W W PUMP JAMESBURYCORP IUTTERFLY 6
150 146.0 144.0 i
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Dock t N2. 50-346 Liccnca No. NPF-3 S:rici No. 1-705 ATTACHMENT 3 OPERATOR INFORMATION NLVE WMBER MAlluFACTURER MODEL NUMBER MOTORRPM OUTPUT MTORIt!E NORN BEM RAi!0 OVERALLACINTOR SPEED IFT.LN.)
RATIO (RPM)
W360 LIMITNGUECORPORAil0N SM40 iM0 25.0 25'8 45:1 72.0:1 W3069 LIMiiOR00ECORPORA110N SM40 1000 32.3 25't 45:1 55.I:1 W3870 LIMiiOROUE CORPORAil0ll 82 40 1000 32.3 25't 45:1 55.5:1 C3071 LIMITOROUECORPOR4i!ON SM40 1000 32.3 25't 45:1 55.B:1 W3072 LIMITOROUECORPORATIN SM140 1000 32.3 3'l 45:1 55.8:1 C308 LIMITOROUE CORPORAil m SM40 1900 25.0 25't 45:1 72.0:1 M599 LIMliDROUECORPORAi!0N 84-1 1000 42.4 60't 34:1 42.5:1 M600 LIMiiOR00ECORPORATION SMI l IMO 42.4 60't 34:1 42.51 DH74 LIMiiOR00ECORFM4fl0N SMI-00 1000 25.2 15'l 45:1 67.5:1 DH71 LIMliOROUE CORPORA 110ll SMI40 1000 25.2 15'8 45:1 67.5:1 DHtA LIMITOR00ECORPORAT10N 84 40 1000 25.2 15'8 45:1 67.5:1 DHis LIMiiM00ECORPORA110N SMI40 1000 25.2 15't 45:1 67.5:1 HP24 LIMiiOROUECORPORAil0ll SMI40 1000 32.3 15't 45:1 55.I:1 HP28 LIMITOROUECORPORATION SMI40 IMO 32.3 15't 45:1 55.8:1 HP2C LIMliOROUECORPORAi!0N SM40 1000 32.3 15't 45:1 55.0:1 HP20 LIMiiOR00ECORPORA110ll SMB40 1800 32.3 15't 45:1
- 55. Bat C31 LIMiiM00ECORPORAi!ON SM40 IMO 17.1 10't 45:1 101.3:1 C32 LIMllDR M CORPORATION SM40 1000 17.1 10't 45:1 101.3:1 Cl4 LIMif0A0UECORPORAil0N 84 4 1800 St.5 40'8 37:1 34.94:1 CIMA LIMii0ROUECORPORATION SMB4 10C0 31.5 40'I 37:1 34.961 C107 LIMITOROUECORPORAi!ON 84 4 189) 51.5 40't 37:1 34.94:1 C107A LIM 110 ROUE CORPORATI0ll SM4 1000 51.5 80't 37:1 34.94:1 Cl342 LIMITOROUECORP0RAi!ON SMC44 1000 26.1 3'l 44:1 67.25:1 Cl343 LIMiiOROUECORPORAT10N SMC44 1000 26.I 3'8 46:1 67.25:1
Dock t No. 50-346 Liccnca No. NPF-3 S;rici No. 1-705 ATTACHMENT 4 TEST DATA VALVE NO. TEST DIR. TEST TESTRETHODJulilFICATION TEST TEli OPEN T0.lW. CLOSED 10.8W. VALVE OPEN/
METHOD D/P D/P MillM MTTIM OPERAKE CLOSED HYM0/
OPEN CLOSED FOUND/LEFT FOUND/LEFT Al FOUM FLOW IPl!D)(Pill)
YES/NO E360 N/A N/A SAME Al AF3869. STAi!C TElilW BHOWS NO N/A N/A 2.5/2.5 1.0/l.0 YES MORADAil0NS M SUFFICIENT MRilN.
AF3869 OPEN HYM0 TEIT BAT. UliN COWiil0N8 AB0VE Mil 0N 1050 N/A 3.0/3.0 1.5/2.0 YEl AF3069 CLOMD FLOW TESTED BAT WITH CON 01110NS AB0VE Mil 8N.
N/A 1200 AF3870 OPEN HYMO TEST SAT. WITH COMITIONS AB0VE Ml!M 1275 N/A 3.0/3.0 1.5/l.5 YES AF3870 CLOSED FLOW TESTED ABOYE Mll M CONDITION SUFFICIENT N/A 1100 BRGINAVAILABLEFORSAillFACTORYOPERATION AT M il6N 0/P.
G3871 OPEN HYMO TEST SAT WITH CON 0lil0NS AB0VE DES!BN 1050 N/A 3.0/3.0 1.5/t.75 YES AF3872 OPEN HYM0 TEST SAT WITH CON 0li!0NS AB0VE DESIGN 1050 N/A 3.0/3.0 1.5/l.75 YES AF300 N/A N/A SAMEAlAF3869.STAllCTESTSHOWN0 N/A N/A 1.0/2.0 1.0/l.0 YES MSRADATIONS M SUFFICIENT MRE!N FOR OPERAil0N Ai M S!SN D/P AF599 BOTH FLOW TEli SAT OPEN/CLOSEB AT MllGN CON 0!T10NS 1400 1400 1.5/3.75 1.0/2.25 N0e AF600 BOTH FLOW TEST SAT. OPEN/CLOM AT MSIGN CON 0li!0NS 1450 1530 1.5/3.75 1.0/2.5 Me DH74 OPEN HYM0 TEliED SAT AB0VE M SIGN CON 0lf!DM 40 N/A 1.75/2.75 1.75/l.75 YEI DH78 N/A N/A SAME Al DH7A liATIC fili SHOW M N/A N/A 1.0/2.75 1.0/l.0 YES i
MIRABATIONS BH94 OPEN HYMO TElifD SAT 400VE DESIM CON 0lil04 54 N/A 1.25/2.75 1.25/2.0 YES DH90 N/A N/A SAME Al M94, ITATIC TEST BHOWS NO N/A N/A l.0/2.75 1.0/l.0 YES M MADATIONS C2A OPEN HYM0 TESTED SAT AB0VE DESIGN CON 0lil0NS 2180 N/A 2.5/2.75 2.5/t.75 YES HP21 N/A N/A SAME AS HP24, STAi!C TEST SHONS NO N/A N/A 2.0/2.75 1.0/l.5 YES MMADATIONS I
C2C N/A N/A SAME Al HP24, liATIC TElf SHOWS NO N/A N/A 1.5/2.75 1.5/2.0 YES DEBRADAfl0NS C20 N/A N/A SAMEAlHP24,liATICTESTSHONSNO N/A N/A 1.5/2.75 2.0/1.5 YES MMADAll0NS HP31 N/A N/A SINILAR TO OTHER SMALL VALVES TESTED, N/A N/A 1.5/2.75 1.5/l.5 YEI STATIC TESTI SHOW NO MIRAMil0NS, M SUFFICIENT MR8!N AVAILAKE FOR MllIN 9/P C32 N/A N/A l!NILAR 10 OTER SMALL VALVES TEliEO, N/A N/A 1.5/2.75 1.5/l.5 YES 11ATIC filit SHOW W M8AADAi!ONS, M SUFFICIENT MR8!N AVAILAKE FOR MS!0N I/P C106 CLOSED FLOW TESTED Ai MI 9/P AffAINAILE, $UFFICIENT N/A 805 2.5/4.0 1.5/1.5 N0e#
MRGIN AVAILABLE FOR MSIGN 0/P. STAflC TElit SHOW NO MORADATIONS MSl064 N/A N/A SAMEAlNS107,liAi!CTElfSHONSNO N/A N/A 2.5/4.0 1.5/2.5 N0ee MIRADAll0NS C107 CLOSED FLOW TEliED Ai MI 1/P ATTAINASLE, $UFFICIENT N/A B45 2.5/4.0 1.5/2.0 YES MRGIN AVAILABLE FOR Ml!BN O/P, AND STATIC TElft SHOW W M BRACATIONS C107A N/A N/A SAMEAlMil07,liAi!CfiltlHONINO N/A N/A 2.25/4.0 1.5/2.25 YES MIRADAi!DNS Sul382 OPEN FLOW TElfE0 At MI AVAILAKE 9/P, luFFICIENT 100 N/A 1.0/t.0 1.0/l.0 YES MAGIN AVAILAKE FOR Mll6N 0/P, ANO lint!C TElfl SHOW N0 N 0RACAfl0NI
Dockst No. 50-346 License No. NPF-3 ATTACIBtENT 4 Serial No. 1-705 TEST DATA VALVE W. TEST 91R. TEST TEST NETH00 JUSTIFICATION TEST TEST OPEN TO.IN. CLOIED TS.BN. VALVE OPEN/
NETHOD D/P D/P IETilM SETilNI OPERAILE CLOSES HYBR0/
OPEN CLOSED FOUW/LEFT FOUW /LEFT A8FOUND FLON (PSID) (PSID)
YES/W
$Nf383 OPEN FLON TESTED AT M I AVAILABLE D/P, SUFFICIENT 100 N/A 1.0/l.0 1.0/l.0 YE8 NARGIN AVAILA8LE FOR DES!6N D/P, An STATIC TESTS SHON NO DESAADATIONS
- Valves inoperable due to incorrect bypass setting and insufficient thrust delivered to overcome D/P. Assessment of inoperable condition provided per LER 85-015.
Valve made operable prior to plant restart from June 9, 1985, shutdown.
- Valves inoperable in the closed direction only, due to torque switch out-of balance by a factor of greater than 2 to 1 in the open direction.
Therefore, the thrust delivered in the close direction was approximately 50% of the value that setting should develop. This reduced the closing thrust to a value below that required to close the valve against the design D/P. Assessment of inoperable condition provided per LER 85-015.
Valve made operable prior to plant restart from June 9, 1985, shutdown.
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