ML13310A917
| ML13310A917 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/26/1983 |
| From: | Baskin K Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| TAC-10853 NUDOCS 8308300568 | |
| Download: ML13310A917 (12) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING August 26, 1983 Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206 Sixty Month Battery Performance Test San Onofre Nuclear Generating Station Unit 1 As you are aware, we are preparing a proposed change to the San Onofre Unit 1 Technical Specifications to revise the battery surveillance requirements consistent with the Standard Technical Specifications. The scope of this proposed change has recently been expanded to revise the limiting conditions for operation and applicable surveillance requirements for the auxiliary electrical supply.
Due to the expanded scope and the effort required in performing a significant hazards analysis, submittal is expected in October of 1983.
In preparation for your review of this proposed change, you requested that we provide the results of the most recent sixty month battery performance test.
We informed you that this test was scheduled for the first quarter of 1983 and that test results would be provided when available.
Unfortunately due to procedural, equipment and schedular problems, completion of the tests required until June of 1983.
The enclosed performance test results establish that all three battery banks have acceptable capacities based on the Technical Specification acceptance criterion of 80% minimum capacity. Battery Banks 1 and 2 exhibited capacities of 100% while the uninterruptable power supply (UPS) battery bank for safety injection valve MOV 850C exhibited a capacity of 84%.
Please note that the UPS battery bank test results should be interpreted based on the following discussion.
8308300566 83082 PDR ADOCK 05000206 P
-PDR
Mr. D.
August 26, 1983 Battery chargers are used to apply two types of charges to battery banks.
The magnitude of the voltage applied by the charger with respect to the battery bank voltage determines the type of charge. Batteries are normally maintained on float charge, which is a low magnitude applied voltage. Periodically, the application of a high magnitude voltage, or equalizing charge, is desirable in order to force all individual battery cells to the same voltage.
In accordance with the Institute of Electrical and Electronics Engineers (IEEE) Standard 450-1980, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations," an equalizing charge is normally applied between three and seven days prior to the start of a battery performance discharge test.
However, an equalizing charge was not applied to the UPS battery bank prior to the subject performance discharge test. In order to perform seismic work during the current outage, the UPS battery charger was replaced with a temporary charger system. The temporary charger system is considered equivalent to the normal UPS charger with respect to the ability to apply a float charge. However, the temporary charger system has insufficient capacity to perform an equalizing charge. Since the performance discharge test was performed under float charge conditions, the battery bank would be expected to exhibit a lower capacity than if an equalizing charge had been applied.
IEEE Std. 450-1980 indicates that the most stringent performance test conditions exist just prior to the application of a scheduled equalizing charge. Omission of the equalizing charge prior to conducting the performance test will produce conservative results and reflect the acceptability of battery maintenance practices. The UPS battery performance test indicates that even under stringent conditions (i.e., lack of an equalizing charge) and normal maintenance, the UPS battery has acceptable capacity.
Please contact me if you have any questions or require additional information.
Very truly yours, Enclosure cc:
J. Burdoine (NRC Region V)
g ATTACHMENT SAN ONOFRE NUCLEAR GENERATING STATION UNITS 1. 2 & 3 MAINTENANCE ORDER
_I CF NO.
The originator shall complete the information in the SHADED areas.
MAINTENANCE ORDER NO.
COPORENT in.
COMPONWNT DESCRIPTION o2
\\ 0S I1 (o I0 IMI/rj4 DISCOVERY DATE E ST. DUN.
P-F TYPE ASSIGNERe.
.N MO MO DAY DAY YR YR PROCLM OC FAILURE DESCRIPTION ES175
\\e3e 2 UPS 010 iol IT LEVEL AREA XE AES DATE c2
/
R/
55 FOR FURTJ..RINF RMATION CONTACT PAX SUPER 15 TR DATE ESTIMATED MANPOWER ATTACHMENTS &
ad CRAFT No.
EST. M...
REVIEWS PLANNERS INST PCTIONS (CONTINUED ON TRAVELER) 17 KF Travetser
)
Mat'I. Req'n.
2 No.
31No. P.
~~/-
~
0.F.P.
U5 Q.A. Review CC 6
Eng. Review
'7.,
.2 7
Pre Staging
- ~
~
SIiLLI I DATE _______
a PLANNER S..
P.M.
IDA QA. REViEWED BY Y
S NO Da, ENG.TUR REIWE1Ys7u POST MAINT. REVIEW REQUESTED YS DT
[ENG. REVIEWED BY UE~><
ESNO DT OREMAN DT FOREMAND TOATE MA INT.
FIELD ENGINEER DATE ASSIGNED TOTh SICNA
.IFT S.N.0.
DATE ACTUAL MANPOWER AUTHORIZED BY
~
,III
.'I I'.jJ.~~XQ CRAFT ND MAN HOURS CAUSE (CONTINUE ON TRAVELER) e o
v Coo
'c\\
,T 2
0 A(CONTINUE ON TRAVELER) 4 Lu I-7 MATERIAL AND SPECIAL TOOLS DESCRIPTION NO.
CAL. DATE Fluke
-c--
-I-S o uo' l be
)-,
R m
t3 A~OV!3 __________
V___
_ _?0MBF DESCRIPTION NO.
CAL. DATE DESCRIPTION NO.
CAL. DATE F1 ke soc 5I&
0 1 0c v'3 FAk As4er
-c C5 COMPLETED BY r TM-DT I-.(c-,
NOTIFICATION)
AT FONEMAN/MAI FIE ERA 1 AL DAEERG SR RI G REVIEW, DT 51 5 r, i4 t 1 51.~ -A CA P fW.DATE PLI.J 1
INFIG REVIEWAT A
6;*&
(t>106
SAN ONOFRE NUCLEAR GENERATING STATION MAINTENANCE PROCEDURE 501-1-2.8
!N IT 1 REVISION 2 PAGE 1 OF 2 ATTACHMENT 9.4 MAINTENANCE DATA RECORD FORM REFUELING INTERVAL BATTERY PERFORMANCE TEST CDM FileNo. CJ20CC-008-FE Battery Bank No.
M.O. No.
Prerequisites Metx(
4C,0
/ 6@3 Signature Date Data Acceptance Recorder/Verifier Step No.
Data Description Values Criteria Signature/Date 6.1.1 Initial Average Battery
_____N/A Temperature 6.1.3.3 Rated Load Amperage (LAu)
/20 per Att. 9.2 6.1.5 Battery Terminal Voltage at Start 130,_7 2125 VDC
/_
6.1.6.1 Calculated Load Amperage
_/
N/A
/__
(LAO) 1.6.5 Battery Performance Test 109A N/A Start Time 6.1.7.2 Performance Test Termination Data:
.2.1 Time of Completion OG:
ft),I N/A o
/
.2.2 Low individual cell voltage cell no.
I7'37
_1.68 VDC
.2.3 Battery Terminal Voltage
_13,R4 105 VDC 0____
.2.4 Test Stopped (manually or hfga ALp' N/A Is automatically
.2.5 Total Elapsed Time to Final 14N, msper Att. 9.2 Vol tage
.2.6 Battery Cells Connected at
((
k59 Termination of Test 6.1.7.4 Calculated Battery Capacity 100 k
280%
o oU 6.1.8 Connections established in Step 6.1.1 have been returned t
to Pre-Test Configuration N/A
- 3. 5 Restoration and Post-Maintenance Checks, Section 6.3 satisfactorily completed.
Signature Date
SAN ONOFRE NUCLEAR GENERATING STATION MAINTENANCE PROCEDURE S01-I-2.8 REVISION 2 PAGE 2 OF 2 ATTACHMENT 9.4 Test Equipment SCE No.
Calibratio Due Dat EL Whe Rkcoc0t voty M I - 3 1 Z3
)o 0,--r c
'3 9
pikt v
ml IS 0( 7-3 d14o A90 14rn"-4ceR 0 931 cn; pq7c-z5-A7-,'3 REMARKS, DISCREPANCIES AND CORRECTIVE ACTIONS:
4NOT iBLoE
'-PE fo a) m 3
4 0 sc. L eice con so, en COMPLETED BY:
3A Q cA DATE: a &-cj-93 REVIEWED BY:
DATE:
sponsible Maintenance Supervisor
SAN ONOFRE NUCLEAR GENERATING STATION MAINTENANCE PROCEDURE 501-1-2.8 UNIT 1 REVISION 2 PAGE 1 OF 2 ATTACHMENT 9.4 MAINTENANCE DATA RECORD FORM REFUELING INTERVAL BATTERY PERFORMANCE TEST CDM Fi1*No. CJ20CC-008-FE Battery Bank No.
M.O. N%. Z338 /
Prerequisites Met
/
[
Signature Date Data Acceptance Recorder/Verifier Step No.
Data Description Values Criteria Signature/Date 6.1.1 Initial Average Battery 7
N/A
____/__-___
Temperature 6.1.3.3 Rated Load Amperage (LAu) per Att. 9.2 yr
/6i-&5 6.1.5 Battery Terminal Voltage at Start 125 VDC 2/1
/d'f-fty 6.1.6.1 Calculated Load Amperage N/A
_____-/-___
(LAc) 1.6.5 Battery Performance Test fjj/%-. N/A
_{_/_
Start Time 6.1.7.2 Performance Test Termination Data:
.2.1 Time of Completion 510 N/A JO O 19
.2.2 Low individual cell voltage cell no.
1'5 lfe A
V 1.68 VDC idit
.2.3 Battery Terminal Voltage tOo.)
105 VDC 01
.2.4 Test Stopped (manually or
_________N/A automatically
.2.5 Total Elapsed Time to Final
)
per Att. 9.2 Voltage
.2.6 Battery Cells Connected at k 59.
Termination of Test 6.1.7.4 Calculated Battery Capacity 100 7 k
280%
/
6.1.8 Connections established in Step 6.1.1 have been returned K
to Pre-Test Configuration N/A
/
3.5 Restoration and Post-Maintenance Checks, Section 6.3 satisfactorily completed.
/
Signature Date
SAN ONOFRE NUCLEAR GENERATING STATION MAINTENANCE PROCEDURE 501-1-2.8 UNIT 1 REVISION 2 PAGE 2 OF 2 ATTACHMENT 9.4 Test Equipment SCE No.
Calibration Due Dat REMARKS, DISCREPANCIES AND CORRECTIVE ACTIONS:
by xor PE~c\\
steP
)),A
-vE c) ty~r bE I AG, D
C, CA AGED,
-rr
.9 PDU'RORHED~ -9'- 73
.***1~4-
-/d-7Y COMPLETED BY:
T
__._DATE:
Ju REVIEWED BY:
pp DATE:
' 6S Res nsible Maintenance Supervisor L
SAN ONOFRE NUCLEAR GENERATING STATION MAINTENANCE PROCEDURE S01-I-2.8 UNIT 1 REVISION 1 PAGE 1 OF 2 ATTACHMENT 9.4 MAINTENANCE DATA RECORD FORM REFUELING INTERVAL BATTERY PERFORMANCE TEST CDM File No. CJ20CC-008-FE Battery Bank No. MO-QsOC OPs M.O. No.
33.L2.
Prerequisites Met L
2
/ 3- /--<
Signature Date Data Acceptance Recorder/Verifier Step No.
Data Description Values Criteria Signature/Date 6.1.1 Initial Average Battery
__So N/A
/5/0 3
Temperature 6.1.3.3 Rated Load Amperage (LAu) per Att. 9.2 3 (6 6.1.5 Battery Terminal Voltage at Start
-125 VDC
/
6.1.6.1 Calculated Load Amperage N/A 2
/
(LAc) 6.1.6.5 Battery Performance Test
_N/A 4 /
Start Time 6.1.7.2 Performance Test Termination Data:
.2.1 Time of Completion N/A J
.2.2 Low individual cell voltage cell. no.,
- T k1.6 VD/6/C
.2.3 Battery Terminal Voltage W~
105 VDC 3-/6
/?
.2.4 Test Stopped (manually or jAAN/A% Y/N/
automatically
.2.5 Total Elapsed Time to Final per Att. 9.2
£/'
31
~
2Al1 Voltage e
.2.6 Battery Cells Connected at
- 59 Termination of Test 6.1.7.4 Calcblated Battery Capacity
?q~~O 6.1.7_4 6.1.8 Connections established in Step 6.1.1 have been returned to Pre-Test Configuration N/A 6.3.5 Restoration and Post-Maintenance Checks, Section 6.3 satisfactorily completed. o B'aSignature Date
SAN ONOFRE NUCLEAR GENERATING STATION MAINTENANCE PROCEDURE S01-I-2.8 UNIT 1 REVISION 1 PAGE 2 OF 2 ATTACHMENT 9.4 fest Equipment SCE No.
Calibration Due Date
-~~~2
-~ 7Sc OE.
REMARKS, DISCREPANCIES AND CORRECTIVE ACTIONS:
COMPLETED BY:
'}__
DATE: 3-I4
-- G3 REVIEWED BY:
L M
nDATE:
Mb16 183 Responsible Maintenance Supervisor
Mr. 0.
August 15, 1983 Reference 1 forwarded revised pages of NUREG-0737 which define the Commission policy on working hours.
The policy required implementation of the revised guidelines by October 1, 1982. References 2 and 3 advised you of the current status of compliance with Commission Policy at San Onofre Nuclear Generating Station. As a follow up to recent telephone discussions with members of the Region V staff, an updated status of compliance is offered.
The NRC policy statement, as detailed in Reference 1, was implemented at San Onofre Nuclear Generating Station on October 1, 1982 by the issuance of procedures defining the guidelines for the use of overtime for the affected plant staff. The policy, as then interpreted, was not applied to the mechanical maintenance personnel at San Onofre Nuclear Generating Station.
Reference 4 provided us with a clarification of your definition of key maintenance personnel.
We have initiated actions to revise the station procedures and expect the revised procedures to be issued by September 1, 1983.
The status of the effort to comply with an NRC request to develop technical specifications on working hours for San Onofre Nuclear Generating Station is as follows:
San Onofre Unit 1 - Reference 5 transmitted your model technical specifications for working hours.
We responded to this letter in Reference 6 by stating that all of the necessary technical specification's, including Limit Overtime, will be submitted sixty days prior to return to power from the current outage.
San Onofre Unit 2 -
The current license condition 19, NUREG-0737 Conditions, b., Shift Manning, provides the technical specification restrictions on the use of overtime at San Onofre Unit 2. The guidelines in this license condition are very similar to those delineated by Reference 1. The status of proposed technical specifications to replace this license condition is as defined in Reference 3. It is estimated, based upon current schedules, that revised technical specifications can be submitted by October 1, 1983.
San Onofre Unit 3.- The technical specification on working hours for San Onofre Unit 3 is defined in Technical Specification 6.2.2., as issued by Reference 7.
The proposed revision to the San Onofre Nuclear Generating Station, Units 1 & 2 Technical Specifications will strictly limit the working hours of the Staff most important to plant safety, the minimum shift crew, to the guidelines of the Commission policy on plant staff working hours.
The remainder of the staff identified in the Commission policy will have their working hours monitored by station management and staffing levels adjusted, if necessary, to reduce the use of any overtime considered to be excessive.
The tasks performed by the staff, other than the operators, are subject to quality assurance, quality control,.startup testing and other forms of independent verification. Thus, the San Onofre Nuclear Generating Station policy on staff working hours, as proposed, will assign the proper level of management attention to each level of safety significance, as it applies to staff working hours. It should also be noted that a proposed revision to the San Onofre Nuclear Generating Station, Unit 3 Technical Specifications, consistent with the above discussion, will also be submitted by October 1, 1983.
0 0
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 K. P. BASKIN TELEPHONE MANAGER OF NUCLEAR ENGINEERING, (213) 572-1401 SAFETY, AND LICENSING August 15, 1983 Director, Office of Nuclear Reactor Regulation Attention: Mr. D. G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Subject:
Docket Nos. 50-206, 50-361 and 50-362 Nuclear Power Plant Staff Working Hours San Onofre Nuclear Generating Station Uhits 1, 2 and 3
References:
- 1. Letter, D. G. Eisenhut, NRC, to All Licensees of Operating Reactors, Nuclear Power Plant Staff Working Hours, (Generic Letter No. 82-12), June 15, 1982 2.. Letter-, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, Docket No. 50-206, NUREG-0737, [tem I.A.1.3 - Shift Manning, Nuclear Power Plant Staff Working Hours, September 28, 1982
- 3. Letter, K. P. Baskin, SCE, to G. W. Knighton, NRC, Docket Nos. 50-361 and 50-362, San Onofre Nuclear Generating Station, Units 2 and 3, January 11, 1983
- 4. Letter, D. G. Eisenhut, NRC, to All Licensees of Operating Reactors, Definition of "Key Maintenance Personnel,"
(Clarification of Generic Letter 82-12) (Generic Letter 83-14), March 7, 1983
- 5. Letter, D. G. Eisenhut, NRC, to All Pressurized Power Reactor Licensees, NUREG-0737 Technical Specifications (Generic Letter No. 82-16), September 20, 1982
- 6. Letter, R. W. Krieger, SCE, to D. M. Crutchfield, NRC, NUREG-0737 Technical Specifications, December 9, 1982
- 7. Letter, D. G. Eisenhut, NRC, to R. Dietch, SCE, G. D. Cotton, SDG&E, San Onofre Nuclear Generating Station, Unit 3 Issuance of Facility Operating License No..NPF-15, November 15, 1982 I
o(0
Mr. D.
August 15, 1983 The discussion above should provide an adequate status of the current actions, with regard to NRC working hour guidelines, at San Onofre Nuclear Generating Station. Until such time as we receive approval of the revised technical specifications discussed above, we will continue to implement the Commission policy, as stated in Reference 1. If you have need for any additional information or desire clarification, please let me know.
Very truly yours, cc:
D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing G. W. Knighton, Chief Operating Reactors Branch No. 3 Division of Licensing J. B. Martin, Regional Administrator Office of Inspection and Enforcement Region V Mr. M'. Padovan, NRC Region V