ML18139B168
| ML18139B168 | |
| Person / Time | |
|---|---|
| Site: | Surry |
| Issue date: | 03/05/1981 |
| From: | Dunn S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139B167 | List: |
| References | |
| NUDOCS 8103170338 | |
| Download: ML18139B168 (42) | |
Text
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e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION 1s*1os 170J31S*
. --~---
~~~----~~-
MONTHLY OPERATING REPORT REPORT NO. 81-02 FEBRUARY, 1981 APPROVED: ~~M-*
MANAGER
.. '"-*'---~-------**---~---**-
- -- -~--~~~-
e CONTENTS Section Operating Data Report - Unit i!l Operating Data Report - Unit 112 Unit Shutdowns and Power Reductions - Unit ill Unit Shutdowns and Power Reductions - Unit 112 Load Reductions Due to Environmental Restrictions Load Reductions Due to Environmental Restrictions Average Daily Unit Power Level - Unit ill Average Daily Unit Power Level - Unit i/2 Summary of Operating Experience
- Unit DI
- Unit 112 Amendments to Facility License or Technical Specifications Facility Changes Requiring NRC Approval Facility Changes That Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require NRC Approval Other Changes, Tests and Experiments Chemistry Report e
Description of All Instances Where Thermal Discharge.Limits Were Exceeded Fuel Handling Procedure Revisions That Changed the Operating Mode Described In The FSAR Description of Periodic Tests Which Were Not Completed Within The Time Limits Specified In Technical *specifications Inservice Inspection Reportable Occurrences Pertaining to Any Outage or Power Reductions Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit ill - Mechanical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance
__,._. ___ -~-----*.. -**
1 2
3 4
5 6
7 8
9 10 11 11 13 13 14 15 16 17 19 20 21 23 24 28
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Section e
-ii-CONTENTS Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or.Reduced Power Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit ill - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance Health Physics Summary Procedure Deviations Reviewed by Station Nuclear Safety and Operating Committee After Time Limits Specified in T.S.
30 32 34 36 38 39
~~-.-*****
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....OPERATING DATA REPORT DOCK3T NO. 50-280 DATE OS MAR 81 COMPLETED BY SUED. DUNN TELEPHONE 804-357-3184 OPERATING STATUS
- 1. l/NIT NAME SURRY UNIT 1
- 2. REPOR'1'ING PERIOD 20181 TO 22881
- 3. LICENSED THERMAL POWER (WT) 2441 1----------
- 4. NA&'i'LATE RATING (GROSS MIE) 847.5 INOTES
- 5. DESIGN EI&CTRICAL RATING (NET WE) 822 I
- 6. MAXINllM D'3PENDABLE CAPACITY ( GROSS MWE) 740
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE) 704
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS NIA
'l-(ITEMS 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS
- 9. POWER LEVEL TO WHICH RESTRICTED. IF ANY NIA (NET MwE)
- 10. REASONS FOR RESTRICTIONS. IF ANY NIA THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL
- 13. REACTOR RESERVE SHUTDCMN HOURS
- 14. HOURS GEN'3RATOR ON-LINE
- 15. l/NIT RESERVE SHl/TDCMN HOURS
- 16. GROSS THERMAL ENERGY GENERATED (MWH)
- 17. GROSS ELECTRICAL ENERGY GENERATED (WH)
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
- 19. UNIT SERVICE FACTOR
- 20. l/NIT AVAILABILITY FACTOR
- 21. UNIT CAPACITY FACTOR (USING MDC N~)
- 22. l/NIT CAPACITY FACTOR (USING DER N!!T)
- 23. UNIT FORCED Ol/TAG:: RATE
- 24. SHUTDCNNS SCHEDULED OVER NEXT' 6 MONTHS (TYPE.DATE.AND DURATION OF EACH)
- 25. IF SHUT DCNN AT END OF REPORT P3RIOD.
ESTIMAT3 DATE OF STARTUP
- 26. UNITS IN TEST STATUS
"(PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
./
672.0 o.o o.o o.o o.o o.o o.o o.o o.o o.o o.o o.o o.o 1416.0 o.o o.o o.o o.o o.o o.o o.o o.o o.o o.o o.o o.o Juir.1}Stts1~.*
717.84.0 42538.5 3731.5 41668.8 3736.2 96389401.0 31301743.0 29699924.0 58.0 olo 63.3 ~lo 58.8 olo 50.3 olo 26.4 o/o FORECAST ACHIEVED
.r:----*
e OPERATING DATA IBPOKr DOCKET NO. 50-281 DATS 05 MAR 81 COMPUTED BY.ijlJE D. DUl~N
- TELEPHONE 804-357-3184 OPERATING STATUS
- 1. UNIT NAME 2
- R:!.""POKrING PERIOD
- 3. LICENSED THERMAL POWER (Mr/T)
- 4. NAMEPLATE RATING (GROSS WE)
- 5. DESIGN ELECTRICAL RATING (NET WE)
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MIE)
- 7. MAXIMUM DEPENDABLE CAPACITY (NET WE)
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THROUGH 7) SINCE LAST REPOKr. GIVS REASONS*:
SURRY UNIT 2 20181 TO 22881 2441.1--------,
- 847.5 !NOTES I
822 I
I 811 I
I 775 I
I NIA
- 9. PrNER LEVEL TO WHICH RESTRICTED. IF ANY NI A (NET WE)
- 10. REASONS FOR RESTRICTIONS. IF ANY NI A
- 11. HOURS IN REPORTING PERIOD 12 *. NUMBER OF HOURS REACTOR WAS CRITICAL
- 13. REACTOR IBSERVE SHUTDOWN HOURS
- 14. HOURS GENERATOR ON-LINE
- 15. UNIT RESERVE SHUTDalN HOURS*
16 ~ GROSS THERMAL ENERGY GENERATED (WH)
- 17. GROSS ELECTRICAL ENERGY GENERATED (WH)
- 18. NET ELECTRICAL ENERGY GENERATED (MWH)
- 19. UNIT SERVICE FACTOR
- 20. UNIT AVAILABILITY FACTOR
- 21. UNIT CAPACITY FACTOR (USING MDC NET)
- 22. UNIT CAPACITY FACTOR (USING DER NET)
- 23. UNIT FORCED OUTAGE RATE
- 24. SHUTDrNNS SCHEDULED OVER NE'X!r 6 MONTHS (TYPE.DATE.AND DURATION OF EA~)
- 25. IF SHUT Da!N AT END OF REPORT PERIOD.
ESTIMATE DATE OF STARTUP
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
~---*- ----*---
THIS MONTH IR-TO-DATE CUMULATIVE s12.o 1416.o*
68664.o 672.0
~416.0 39200.0 o.o o.o o.o 672.0 1416.0 38552.6 o.o o.o o.o 1637682.0 3452663.0 89907324.0 536035.0 1130160.0 29369154.0 508432.0 1072035.0 27850523.0 100.0 o/o 100.0 o/o 56.1 o/o 100.0 o/o 100.0 o/o 56.1 o/o 97.6 o/o 97.7 o/o 52.3 o/o 92.0 o/o 92.1 o/o 49.3 o/o 0.0 0.0 19.* 2 o/o SNUBBER INS~CTION & SPRING..
MAINTENANCE -.'APRIL, 1981 -.*10 DAYS FORECAST ACHIEVED.
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SUED. DUNN UNIT NAME l>ATE COMl'I.ETED IIV TELEI IIONE 357-3184 Cause & fuuci:llvc Acl Inn I u rrcvi:111 Rccuocncc Continuation of shutdown for steam generator connnenced replacement outage which 9-14-80.
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I Cause & Curiecllve Acl 11111 1t1 rrevcnl flccurrcnce At 1415.* while performing a periodic test on excore detector N-43, the control pow-er fuse failed causing a NIS turbine.run-back.
The turbine was placed in manual control stopping the runback at 57%
reactor power, Trouble-s.hooting failed to determine the cause of the blown fuse and no problems were found in the detec-tor channel.
At 1553 a power increase began and the unit was at 100% power at 2000.
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e e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 1 MONTH: February DATE TIME HOURS LOAD 2 MW REDUCTI0NS 2 MW HWH REASON.
None during this reporting ptariod.
~
MONTHLY TOTAL
.,._Plf;!"l'!!-!+ ___..!!.£!...._.
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e e LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT N0.2 MONTH: February, 1981 DATE Tllfi:
HOURS LOAD 1 MW REDUCTIONS 1 MW MWH REASON None dt ring this reportiI g period.
MONTHLY TOTAL
~------:-:-~--~,..,_,_~__::_:____,_____,_.~--
MONTH:
FEBRUAHr 81 DAI 1
2 3
4 5
6 7
8 9
10 11 12 13 14
~----------~--
DOCK.BT NO UNIT DATS COMPL:!.""'TED BY AVERAGE DAILY UNIT ~
LSVEL e
50-280 SURRY I 3-1-81
..SUE D. -i>UNN AVERAGE DAIU P(MER LEVEL AVERAGE DAIU PQi/ER LEVEL
(/r!ilE-NE'r)
DAI (ftNE-NE'r) o.o 15 o.o o.o 16 o.o
-o.o 17 o.o o.o 18 o.o o.o 19 o.o o.o 20 o.o o.o 21 o.o o.o 22 o.o o.o 23 o.o o.o 24 o.o o.o 25
. o.o o.o 26 o.o o.o 27 o.o o.o 28 o.o
~
DAILY UNIT POWER L'SVEL PORN INSTRUCTIONS ON THI£ ~ORM, LIST THE AVERAGE DAIU UNIT POWER LEVEL IN WE-NE'r FOR EACH DAY IN THE IBPORTING MONTH. THESE FIGl/RSS WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT B:t USING MAXIMUM DEPENDABLE CAPACITY FOR THE NE'r ELECTRICAL RATING OF TBS UNIT. THERE NAY BE OCCASIONS WH?N TH'S DAILY AVERAGE PrMER EXCEEDS THE 100 °/ 0 LINE (OR THS RESTRICTED PCMER LEVEL LIN'S). IN SUCH CASES. THE AVERAGE DAIU UNIT P(MER OUTPUT SHEET SHOULD BE FOOTNOTED TO SXPLAIN THE APPARENT ANOMALY *
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e e DOCKET NO 50-281 UNIT SURM II DATE.
3-1-81 COMPL:.--PED BY
$W: ;D. D~_;
AVERAGE DAILY UNIT POWER l&VEL MONTH:
FEBRUARY 81 AVERAGE DAILY POWER LEVSL AVSRAGg DAILY POWER LEVEL DAI (WE-N'!:'r)
DAY (NilE-NE'l')
1 758.5 15 757.0 2
756.3 16 757.9 3
758.9 17 756.5 4
759.7 18 758.6 5
758.9 19 755.6 6
759.3 20 752.4
- 7 760.6 21 752. 7 8
760.2 22 757.5 9
759.3 23 756.4 10 759.7 24 730.3 11 759.9 25 757.2 12 758.8 26 757.0 13 757.9 27 756.8 14 756.1 28 754.8 DAILY UNIT POWER. LEVEL FORM INSTRUCTIONS ON THIS FORM. LIST THE AVSRAGE DAILY UNIT P(JWER LEVEL IN WE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGllRES WILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING MONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NET ELECTRICAL RATING OF THE UNIT. THERE MAI BE OCCASIONS IIHEN THE DAIL! AVERAGE PCMER EXCEEDS THE 100 °/ 0 LINE (OR THE RESTRICTED POWER LEVEL LINE). IN SUCH CASES. THE AVERAGE DAILY UNIT PCMER OUTPUT SHE'!:'r SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.
~- ----..,-------*
~RY. OF OPERATING EXPERIENCE e February, 1981 Listed below in chronological sequence by experiences for this month ~hich required load ificant non-load related incidents.
unit is a summary of operating reductions or resulted in sign-UNIT 1 February 1 This reporting period begins with the unit at cold shutdown for steam generator replacement and major.design changes.
February 28 This reporting period ends with the unit at cold shutdown for steam generator replacement and major*.design changes.
UNIT 2 February 1 This reporting period begins with the unit at 100% power.
February 24 At 1415, while the Instrument Technicians were performing a periodic test on excore detector N-43, the control power fuse blew causing a NIS turbine runback.
The control room operator piaced the turbine in manual control stopping the runback at 57% reactor p*ower.
At 1420 a power increase began and was halted at 1528 with the unit at 70%'
power.
The instrument technicians went through their "trouble-shooting" procedure to determine the cause of the blown fuse.
They found no problems in the detector channel and.: at.. 1553 a power increase began.
The unit was at 100% power at 2000.
February 28 This reporting period ends with the unit at 100% power.
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AMEIID?IBNTS TO FACILITY LICENSE OR TECHNICAL SPE ICATIOUS February, 1981 The Nuclear Regulatory Commission issued, on December 18, 1980, Amendment Uo. 63 to the Operating License for Surry Power Statiqn, Units No. 1 and No. _2.
The December 18, 1980 Condition of the License has been designated as Technical
- Specification Change No. 69.
The change implements a requirement to follow a guard training and qualification plan in accordance with 10 CFR 73.55(b) (4).
Of significance, paragraph 3.K of the Surry Unit No. 1 and Uo. 2 Operating Licenses is amel;ld:ed to r.ead as follows:
"3.K The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Nuclear Security Personnel Training and Quali-fications Program, including amendments and changes made pursuant to 10 CFR 50.54{p) *. The approved Nuclear Security Personnel Training and Qualifications Program consists of a document withheld from public disclo-sure pursuant to 10 CFR 2.790(d) identified as "Surry Power Station Nuclear Security Personnel Training and Qualification Program" dated.September 15, 1980.
The Nuclear Security Personnel Training and Qualifications Program shall be fully implemented in accordance with 10 CFR 73.55(b) (4), within 60 days of this approval by the Commission.
All security personnel shall be qualified within two years of this approval."
The Nuclear Regulatory Commission issued, on February 9, 1981, Amendment No. 64 to the Operating License for Surry Power Station, Units No. 1 and No. 2.
The changes have been designated as Technical Specification Change No. 70.
Of significance, the changes incorporate a clarification of the definition of "operable" and add general Limiting Conditions for Operation with general action statements.
In addition, paragraph 3.B of the Operating Licenses is amended to read as follows:
"B.
The Technical Specifications w;.:......,.~ --
The Technical Specifications contained in Appendices A and B, as revised through Amendment ~o. 64, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the "Technical Specifications." *
... e...
~CILITY CHANGES REQUIRIUG NRC APPROVAL e
February, 1981 None during this reporting period.
FACILITY CHAUGES THAT DID NOT. REQUIRE NRC APPROVAL D/C 77-19 Make-up Water Treatment Modification The filter backwash settling pond (77-19G) portion of this design change has been implemented.
Summary of Safety Analysis:
There are no safety implications for the proposed changes as _the operation of safety related equipment will not be affected.
D/C 78-08 Fire Protection Modification UNIT 1,2.
1,2
'!'he 78-081 portion involving the installation of a heat detector in the gaseous waste charcoal filters to alarm in the security building control room was implemented.
Summary of Safety Analysis This modification increases surveillance of the gaseous waste charcoal filters to reduce the chances of a £ire related accident.
D/C 78-10. Condensate Polishing Addition Another po~iion of this design change involving maj.or mechanical Installation and erection of pipes and hangers (78-lOK) was implemented.
Summary of Safety Analysis This modification neither constitutes an unreviewed safety question nor requires a change to Technical Specifications.
D/C 78-44 Steam Generator Blowdown Treatment System The piping portion (78-44B) of this design change has been implemented.
Summary of Safety Analysis The overall safety reliability and performance of the steam generator b"lowdown system will be improved by this modification.
The design specifications will meet or exceed the specifications of the existing
. system *
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- e Facility Changes That Did Not Require NRC Approval (Continued)
D/C 79-65 Construction Site Sewage Treatment This design change disconnected the construction site's sewage line from the septic tank and drainage fields.
The sewage line is not tied into the plant sewage treatment system.
Summary of Safety Analysis This modification will not affect any operation of safety related equipment.
D/C 79-75 Emergency Egress Lighting Emergency lighting fixtures with the following features have been provided:
a)
Self contained power packs, including permanently sealed lead-acid battery and solid state charge.
b) Directionally adjustable high efficiency halogen lamps.
c)
Solid state monitoring circuits which automatically connect lamps to battery upon failure of a C power.
d)
Front mounted test and control switches indicating lights and battery voltage indicator.
These fixtures, strategical~ placed, provided adequate lighting for fire fighting efforts and safe personnel egress from the affected area.
Summary of Safety Analysis This modif~cation enhances the fire fighting effort and safe egress of personnel and does not create an unreviewed safety question.
~1'-_,,.,..... *** _____ _
UNIT NA 1,2
.. -~-
--*-----'~-- ------
---~-..:.....:._....._ ______.-~z*. -------*-
- A
'TS AND EXPERIMENTS REQUIRING W NRC APPROVAL FEBRUARY, 1981 None during this reporting period.
TEST AND EXPERIMEUTS*THAT DID NOT REQUIRE NRC APPROVAL None during this reporting period.
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- ....,....---,,~~,...,,.....-----.---.,---------
~ 0Tillll'CHANGES, TESTS AND EXPERIMENTS~
February, 1981 None during this reporting period.
- µ t..~.....,
L PRIMARY COOLANT ANALYSIS MAXIMUM Gross Radioact., µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml Iodine-131, µCi/ml 1-131/I-133 Hydrogen, cc/kg Lithium, ppm Boron-10, ppm+
Oxygen-16, ppm Chloride, ppm pH@ 25°C Sl:RRY PO.*:ER STATION CHEr1ISTRY REPORT February, 19 __fil,_
T.S. 6.6.3.* d UNIT NO. l MINIMUM AVERAGE Note (A)
+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL
~
RELEASES, POUNDS T.S. 4.13.A... p,;"
O*
Boron 0
e UNIT NO.
MAXIMUM MINIMUM 2 *.68E-1 S.SlE-:2 0.1 0.1 2.86E-1 2.60E-1 3.52E-3 1.SOE-3
.8417
.5983 54.o. (c)'
33.6 2.30 1.95 125 115 0~000 0.000 0.05 0.05 6.98 6.84 309 Phosphate Sulfate 50% NaOH Chromate 0.36
__ ;::;,.,:.;~-----
0 Chlorine *~ _ __:0::...._ ____ _
Remarks~ (A) Unit 1 at*csn, defueled and drained for SGRP.
(B) Reactor run-back to 39% due to blown fuse in instrumentation.
(C) ReQuested Operations reduce H2 pressure on VCT.
2
('BJ AVERAG:
1.68E-0.1 2.68E-2.29E-
.7344 42.1 2.14 121 0.000 0.05 6.91 These levels of chemicals should present no major adverse environmental impact.
-. -~ '-~.
,----~~.
.. A D~IPTION OF ALL INSTANCES WHERE W THERl1AL DISCHARGE LIUITS WERE EXCEEDED February, 1981 Due to the impainnent of the circulating water-* system on the following days, the thermal discharge limits were exceeded.as noted.
February 1, 1981 Exceeded 0
150F llT across station February 2, 1981 Exceeded 15 F llT across station 0
February 3, 1981 Exceeded 15 F llT across station 0
February 4, 1981 Exceeded 15 F llT across stat.ion 0
February 5, 1981 Exceeded 15 F llT across station.
0 February 9, 1981 Exceeded 15 F llT across station 0
February 10, 1981 Exceeded 15 F llT across station February 11, 1981.
Exceeded 15°F llT across station February 12, 1981 Exceeded 15°F llT across station February 13, 1981 Exceeded 15°F llT across statio.n February 14, 1981 Exceeded 15~F l:lT across station February 15, 1981 Exceeded 15 F llT across station 0
February 16, 1981 Exceeded 17.5 F llT across station February 17, 1981 Exceeded 15°F llT across station
- Indicates dates where station fj.T was less than 15.0°F across station for sometime during the day.
The /j.T excursions were allowable under Technical Specification 4.14.B.2.
There were no reported instances of adverse environmental impact.
On February 24, 1981 the temperature change at the station discharge exceeded 3°F per hour due to a NIS turbine runback on Unit 2.
These events were allowable in accordance with Technical Specification 4.14.
There were no reported instances of adverse environmental impact *
.. -----.----~---
FUEL HAlIDLmG UNIT No. 1 February, 1981 *.
None during this reporting period.
- -***-**-----------****----.~---.--
I
' FUEL HAlIDLIHG UNIT N0.2 February, 1981 None during this reporting period *
*- -~---
1,*-
- -------.... *-~~
PR~DURE REVIS;~~~ THAT CHANGED TH~
OPERATING MODE DESCRIBED IN THE FSAR February, 1981 None during this reporting period.
r
*---------~~- -*----*
DESCRieON OF PERIODIC TESTS WHICH WERJ..
COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS February; 1981 PT 24.4J Fire Protection Systems (Trailers). Monthly, was performed on January 21, 1981.
This PT devi~tion was incorrectly routed straight to station records and thus the deviation was bypass-ed and is late. Personnel involved have been instructed to be alert for deviation review requirements.
-.. -.. _--~-=~~~-
UNIT 1 INSERVICE INSPECTION February., 1981 e
The Westinghouse program for inservice_inspection is still in progx::ess with no major indications being noted.
An inspection of ASME CLASS III han-gars and component supports is still being*conducted.
An ultrasonic inspec-tion was completed on all major bolting.associated with the LP and HP turbines also other inspections are being.conducted to assist in the maintenance work associated with the turbine overhaul.
Conducted a random eddy current inspection of feedwater heater exchangers lA & lB, 2A & 2B, 3A & 3B, 4A & 4B, SA & SB, 6A & 6B.
From this inspection, the only reportable indications were found in heat exchangers SA, 6A and 6B.
A further investigation will be conducted after startup testing of the conden-sate system.
Conducted a raaiographic inspection on_6 welds in /fl safeguards on main steam piping; indications were noted as corrosion and turned over to mechanical maintenance for resolution and disposition.
Conducted eddy current on the new steam generator lower shell tubing to complete the data baseline.
UNIT 2 Conducted an ultrasonic examination of 6 welds in ft2 safeguard on main 1
steam piping - no indications were reported.
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Ill RE TABLE OCCURRENCES PERTAINING T-ANY OUTAGE OR POWER REDUCTIONS February, 1981 None during this reporting period.
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- ,.. HEALTH PHYSICS February, 1981 There was no single release of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10%
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PROCEDU EVIATIONS REVIEWED BY STATION SAFETY OPERATING COMMITTEE AFTER TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS February, 1981 None during this reporting period.