ML20238E865
| ML20238E865 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/01/1987 |
| From: | Cox D SOUTHERN CALIFORNIA EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| IEB-85-003, IEB-85-3, NUDOCS 8709150256 | |
| Download: ML20238E865 (17) | |
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F f [8 RECElVED NRC Southem Califomia Edison Company REGION y 1981 SEP -2 A 11: f f 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 I
September - 1,1987 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210
-Halnut Creek,~CA 94596-5368 Attention: Mr. J. B. Martin, Regional Administrator
Dear Sir:
Subject:
Docket Nos. 50-206, 50-361 and 50-362 San Onofre Nu lear Generating Station Units 1, 2 ano 3
References:
'1)
IE Bulletin 85-03, " Motor-0perated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings,"
dated November 15, 1985 l
- 2) May 19, 1986 letter from J. L. Rainsberry (SCE) to J. B. Martin (NRC - Region V), Subject'.
Docket Nos. 50-206, 50-361 and 50-362, San Onofre Nuclear Generating Station, Units 1, 2 and 3
- 3) June 30, 1987 letter from D. F. Kirsch (NRC - Region V) to M. Medford (SCE)
- 4) August 12, 1987 letter from H. O. Medford (SCE) to Richard l
Kiessel (NRC),
Subject:
Same as Reference 2.
By reference 1 the NRC requested that Southern California Edison (SCE) develop and implement a program to ensure that switch settings on certain l
i safety-related motor operated valves (M0V's) at San Onofre are selected, set and maintained correctly to accommodate the maximum differential pressures expected on. these valves during both normal and abnormal events within the design basis.
By Reference 2, SCE provided a description of the program l
which met the requirements of reference 1.
Reference 4 responded to your request for' additional inforrtation in Reference 3.
8709150256 870901 PDR ADOCK 05000206 O
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W Mr. ~ J. B. Martin September 1,1987
' Reference 1 required that safety related valves in only the High Pressure Sa.fety Injection (HPSI) and Auxtlary Feedwater (emergency feedwater) systems
-be subjected to this upgrade program. When the San Onofre MOV program was established in February of 1986, there were two objectives:
- 1) Complete implementation of this program for.all valves required by Reference 1 at the next refueling outage or prior to November-1987.
- 2) Complete implementation of this program for all other safety related (non-butterfly type) valves no later than the subsequent refueling outage.
The San Onofre program consists of the following major elements:
- 1) The design basis of each valve was documented by the Nuclear Systems Engineering group.
- 2) The torque and thrust requirements for each valve were calculated by Kalsi Engineering in Sugarland Texas.
- 3) Design basis tests of one valve in each valve group were performed.
The test data was reviewed and extrapolated as necessary when the in plant test conditions did not allow development of the full design differential pressure.
- 4) Design change documents were issued by the Station Technical Department to:
A)
Separate the torque switch bypass contacts from the open/close contacts by moving the torque switch bypass contacts to rotors 3 and 4.
Torque switch bypass adjustment is then possible ithout compromising the open/close limit switch adjustment.
B)
Determine correct switch settings using the calculated thrust requirements and data from the design basis test.
C)
Add the switch settings to the valve electrical elementary diagram.
- 5) The Station Maintenance Department has conducted valve rewiring, inspection, spring pack changes and testing of each valve using MOVAT's INC. test equipment.
The current status of the MOV program is as follows:
Valve Typt U1 U2 U3 Bulletin Valves Completed 15 23 23 Supplemental Valves Completed 2
44**
84*
Supplemental Valves Scheduled
_fL 45***
TOTAL 25 112 107
- Includes 4 Butterfly Valves and 1 Balance of Plant (B0P) Valve
- Includes 4 Butterfly Valves
- Includes 5 B0P Valves
- w..
3 Mr. J. B. Martin
- 3'-
September 1, 1987.
As required by Action f. of Reference 1 and to meet the SCE commitment in j
Reference 2, the program completion report (Enclosure 1) is hereby submitted t
to the NRC.
This report 1) verifies completion of the requested program, IE Bulletin 85-03 Actions "b", "c", and "d", 2) summarizes the findings of
' valve operability prior to any adjustments as a result of the bulletin, and
- 3) summarizes the data in accordance with the bulletin Table 2, Suggested Data Summary Format.
1 SCE is presently. assembling the remaining data developed from the San Onofre MOV program which is for all remaining safety related (non-butterfly type)
MOV's.
This part of the San Onofre MOV program is above and beyond the reference 1 requirements. When this data is compiled and the necessary.
reviews are completed, it will be transmitted to you as a supplement to this submittal.
SCE is confident that after completion of this Motor Operated l
Valve Program, that valve malfunctions which prompted the issuance of reference 1 will have been eliminated from the San Onofre Nuclear Generating Station.
Subscribed on this /M day of
/, 1987.
t Respectfully submitted, i
SOUTHERN CALIFORNIA EDISON COMPANY By:
D.' L. Cox
/
Supervising Engineer, Nuclear Licensing Subscribed and sworn t before me this
_yf day of A /W7.
OFFICIAL SEAL I
@wy$7NGE AGNES CRABTREE I
nW W>
SC U i
- ry Public in and for the County of No comm. Exp. Sep. u.1990 i
L Angeles, State of California
~-
My Commission Expires:
/g/Ud Enclosure cc:
U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Hashington, D.-C.
20555 cc:
H. Rood, NRR Senior Project Manager, San Onofre Units 1, 2 and 3 J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 t
't' 9
.s RESPONSE TO IE BULLETIN 85-03
" MOTOR OPERATED VALVE COMMON MODE FAILURE DURING PLANT TRANSIENTS DUE TO IMPROPER SWITCH SETTINGS" SAN ONOFRE NUCLEAR GENERATING STATION UNITS 1, 2, AND 3 l
IE Bulletin 85-03 requested Southern California Edison to review the design basis of and to develop and implemer.t a program to ensure that switch settings on high pressure safety injection and auxiliary feedwater system safety related motor operated valves are selected, set, and maintained correctly to accommodate the maximum differential pressure expected on these valves during both normal and abnormal events within the design basis. Valves selected are those that are required to be tested for operational readiness in accordance with 10CFR50.55a (g). Provided below is the response for the San Onofre Nuclear Generating Station, Units 1, 2 and 3.
Action "a" l
" Review and document the design basis for the operation of each vaive.
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 submittals such as FSAR analyses and fully-approved operating and emergency procedures, etc.).
When determining the maximum differential pressure, those single equipment failures and inadvertent equipment operations (such as inadvertent valve closures or openings) that are within the plant design basis should be assumed."
Response "a" SONGS Units 1, 2 and 3 design and operating conditions have been evaluated for the required valves as requested.
The resulting data are presented in Attachments 1, 2, and 3, " Valve Data Summary", for SONGS Units 1, 2, and 3 respectively.
Action "b" "Using the results from item "a" above, 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 bypass, position limit, overload) for each valve operation (opening and closing).
If the licensee determines that a valve is inoperable, the licensee shall also make an appropriate justification for continued operation in accordance with the applicable technical specification."
t_
- n' w
e
-2 Response "b" The plan used.to accomplish Action "b" was as follows:
1)
Review the bases provided'in item "a".
2)
Calculate torque and thrust requirements for each valve listed in Valve Data Summary.
3)
- Revise Limitorque control circuit and wiring such that the torque switch bypass limit switch and open/close limit indicating switches-are on separate rotors,-where applicable.
4)
Review measured values from the maximum differential pressure test and calculations for torque and thrust and then establish correct switch settings.
5)
For valves which were determined to be inoperable, the justification for continued operation was established or corrections made.
Action "c"
" Individual valve settings shall be changed, as appropriate, to those established in item "b", above. 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'" above 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 differential pressure cannot practicably be performed. This justification should include the I
al ernative to maximum differential pressure testing which will be used to ve, fy the correct settings.
Note:
This bulletin is not intended to establish a requirement for valve testing for the condition simulating a break _in the line containing the valve.
However, to the extent that such valve operation is relied upon in the design basis, a break in the line containing the valve should be considered in the analyses prescribed in items "a" and "b" above.
The resulting switch settings for pipe break conditions should be verified, to the extent practical, by the same methods that would be used to verify other settings (if any) that are not tested at the maximum differential pressure.
Each valve shall be stroke tested, to the extent. practical, to verify that the settings defined in item "b" above have been properly implemented even if testing with differential pressure can not be performed".
Response "c" The work to accomplish Action "c" was as follows:
Individual valve settings were changed, where applicable, by performing valve analysis utilizing Motor Operated Valve Analysis and Test System j
(MOVATS) on each valve listed in the Valve Data Summary.
Maintenance
'l Orders were used to conduct all work and document "as found" and "as
i 7
Those valves found inoperable were documented utilizing a left" conditions.
non-conformance report (N'CR), appropriate Technical Specification action statements were followed and corrections were made.
i Response "c" (Continued)
All valves were stroke tested to verify that the settings established For one valve in each group of valves with the same design were proper.
basis, the stroke test was performed under maximum differential pressure In some cases the as listed under " Test d/p" in the Valve Data summary.
actual system pressure developed during testing was less than the design I
For valves where plant pressure listed under " Design Basis d/p."
conditions would not allow a flow test, stroke tests with hydrostatic Since only thrust values above the pressure applied were performed.
pre-load of the belleville spring pack can be quantified, those values are listed as " " the pre-load thrust.
Action "d"
" Prepare or revise procedures to ensure that correct switch settings are Ensure that determined and maintained throughout the life of the plant.
applicable industry recommendations are considered in the preparation of these procedures.
This item is intended to be completely consistent with action item 3.2,
" Post-Maintenance Testing (All Other Safety-Related Components)," of Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATHS Events." These procedures should include provisions to monitor valve This is particularly performance to ensure the switch settings are correct.
important if the torque or torque bypass switch setting has been significantly raised above that required."
Response "d" l
The following procedures have been enhanced to include details for inspection, adjusting and documentir.g the limit, torque and bypass settings for Limitorque i
MOVs:
"Limitorque Model SMB-000, SMB-00 and 58-00 Disassembly, 50123-I-6.7 l
Inspection, Repair, Assembly and Adjustment"
" Actuators - Limitorque Model SMB-0 through SMB-4 and SB-0 S0123-I-6.8 through SB-4 Disassembly, Inspection, Repair and Assembly"
" Actuators - Motor Operated Valve Analysis and Testing System, S0123-I-8.313 MOVATS" All associated elementary diagrams for the listed valves have been revised to show required contact arrangement and switch settings.
l'
_a_
F Action "e" "Within 180 days of the date of this bulletin, submit a written report to the l
NRC that: (1) reports the results of item "a" and (2) contains the program to accomplish items "b" through "d" above including a schedule for completion of l
these items.
The schedule shall ensure that these items are completed as soon I
as practical and within two years from the date of this bulletin".
I Response "e" 4
The requested report was submitted by letter, J. L. Rainsberry (SCE) to l
J. B. Martin (NRC), dated May 19, 1986.
Action "f"
l Provide a written report on completion of the above program.
This report should provide (1) a verification of completion of the requested program, (2) l a summary of the findings as to valve operability prior to any adjustments 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.
Table 2 should be expanded, if appropriate, to include a summary of all data required to evaluate the response to this bulletin.
Response f" The requested report with valve summary and findings are Attachments 1, 2 and 3.
t i
1 Att*.....ent 1, Valve Data Summary, San Onofre Unit 1
., Valve Data Summary, sin Onofre Unit 2
!, Valve Data Summary, San Onofre Unit 3 8882F i
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