ML20062B144

Monthly Operating Repts for Sept 1978

ML20062B144
Person / Time
Site:	Calvert Cliffs
Issue date:	10/15/1978
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20062B138	List: ML20062B135 ML20062B144
References
NUDOCS 7810230182
Download: ML20062B144 (20)

Text

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OPERATING DATA REPORT I

DOCKET NO.

Cn 't17 DATE 10M cD78 COMPLETED BY S D Weson TELEPHONE 301-pb.42ho OPERATING STATUS 1

1. Unit Name:

c=1=e-+ c1_4+n um

2. Reporting Period:

September. 1978

3. Licensed Thermal Power (MWt):

2700

4. Nameplate Rating (Gross MWe):

910

5. Design Electrical Raimg (Net MWe):

8h5 U

6. Maximum Dependable Capacity (Gross MWe):

810

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons.

9. Power Lesel To which Restricted,If Any (Net MWe):

hna

10. Reasons For Restrictions.lf Any:

N/A This Month Yr to-Date Cumulative 720 6,551 29,796

!I. Hours in Reporting Period (20.0 h,h83.0 2h,186.6

12. Number Of Houn Reactor Was Critical

13. Reactor Resene Shutdown Hours 0.0 h8.7 586.6 720.0 h,31h.9 23,706.6

14. Hours Generator On-Line

15. Unit Resene Shutdown llours 0.0 0.0 n_n

16. Gross Thermal Energy Generated (MWH) 1.773.2h0.0 10.2h 8.60h. 8 C6.717.qpo.h

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17. Gross Electrical Energy Generated (MWH) 57h&6__ _ _.

3.385.152 18.860.096

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18. Net Electrical Energy Generated (MWH) 5h9,22h 3,218,876 17'.997.7h1 -'

100.0 65.9 79.6 l

19. Unit Senice Factor 100.0 65.9 79.6

20. Unit Availability Factor 94.2 60.7 7h.6

21. Unit Capacity Factor (Using MDC Net)

2. Unit Capacity FactoriUsing DER Net) 90.3 58.2 71.6 0.0 11 3 6.9

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each):

Calvert Cliffs No.1 is scheduled for a planned outage starting April lh.1979.

and will be 6-weeks in duration for general inspection and refueling.

25. If Sht. Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status tPrior to Commercial Operationi:

Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPERAT:ON 7 hoa-) o in R

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OPERATLNG DATA REPORT DOCKET NO.

50-318 DATE 10/15/78 COMPLETEI' BY R. n W eson TELEPHONE 101-9th 42hD OPERATING STATUS Notes I. Unit Name:

cnivart c14 fr. un _ o

2. Reporting Period: Septernber.1978

3. Licensed Thermal Power (MWt):

2700

4. Nameplate Rating (Gross MWet 911 8h5

5. Design Electrical Ratmg (Net MWe):

6. Maximum Dependable Capacity qGross MWe):

Ob5 810

7. Masimum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted. If Any (Net MWe):

Mana

10. Reasons For Restrictions,if Any:

N/A This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 79n 6;591 13;1g1

12. Number Of Hours Reactor Was Critical 3h2.5 4.748.9 11 <17_1

13. Reactor Resene Shutdown Hours 0.0

' 72.5

'219.h

14. Hours Generator On.Line 339.5 4.67h.6 11_aql 7

15. Unit Resene Shutdown flours

'O.0 0.0.

'~ 0.0

16. Gross Thermal Energy Generated (MWH) 817,hlh.0 13,038,516.2 27.367.709.0

17. Gross Electrical Energy Generated lMWHI 259,620 h,319,138 9,073,520

18. Net Electrical Energy Generated (MWHI 2h5,181 h.107.9h7 8.6h9.301 ' /

19. Unit Senice Factor h7.2 86.6 K1

~

20. Unit Availability Factor h7.2 86.6 86_1

21. Unit Capacity Factor (Using MDC Nett h2.0 77.h 81.2

22. Unit Capacity Factor IUsing DER Net) 60.3 7h.2 77.8

23. Unit Forced Outage Rate 5.8 8.3 6.4

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:

Corr:rnenced planned outage on Seotember 16_. 1978. rne annaval i n.,n.,.+ 4 mn.-a refueling.

2b if Shut Down At End Of Report Period. Estimated Date of Startup: In_21 78

26. Units in Test Status (Prior o Commercial Operation):

Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPERATION (9/77) i

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AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.

Cn. 417 UNIT Calver t Cliffs #1

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DATE 10/15/78 COMPLETED BY S D M rson TELEPHONE 301-23h-62hO l

l MONTH Sentember. 1978 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL i

(MWe Net)

(MWe Neti 1

' 777 17 699 2

769 is 731 l

761 19 827 3

4 725 20 791 5

781 21 820 6

801 22 793 7

808 825 23 s

735 24 670 9

667 25 8k2 10 69h 26 836 11 791 27 770 12 787 23 666 13 756 29 729 r

-,- /

14 768 30 813 15 757 3

16 78h INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole rnegawatt.

(9/77)

ot;.

l AVER AGE D AILY UNIT POWER LEVEL DOCKET NO.40-118 UNIT Calvert Cliffs #2 DATE 10/14/78 COMPLETED BY S. D. Merson l

l TELEPHONE 301-23h-52h0 l

l d

i MONTil

- September, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe-Net)

I

' 775 17 2

778 Ig 3

778 19 4

775 20 5

77h 21 6

767 22 7

572 23 8

127 24 9

670 25 10 768 26 1I 766 27 12 658 28 13 697

(

l 29 14 701 30 15 683 31 16 l

INSTRUCTIONS l

On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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1 DOCKET NO.

40 11 R UNIT:IUTDOWNS AND POWER REDUCTIONS UNIT NAME N 1 va e+ c14 cc. No. 2 DATE 1965/78 M ETED BY s n_ mmnn REPORT MONTH up+-a..,1978 TELEPHONE in1 >Th.<%n e.

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YE Licensee E r, ft, Cause & Corrective No.

Date k

3g i

is5 Event g

Q Actiim to f

E Reporia mo Prevent Recurrence 3 ;g =g H

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78-17 780907 F

20 7 A

1 IER - 031 SF VALVEI Forced outage due to low boron concen-tration in No. 21 & 22 safety injec-tion tanks. This resulted from in-leakage of reactor coolant through the safety injection tanks check valves.

78-18 780916 S

359.8 C

1 N/A Scheduled outage for reactor general inspection, refueling and unit inspec-tion.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LERI File INUREG-D Regulatory Restriction 4-O:her (Explain) 0161)

E-Operator Training & Ucense Examination F-Administrative 5

G Operational Error (Expla'ih)

Exhibit I - Same Source (9/77) llother (Explain) x3

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Anendment I*o. 2 to License No. DPR-69, Paracraph 2.C.6, specifies additional reactivity and power distributica curveillance, to vit:

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A3ditional Reactivitv eni Power Distribution Surveillance j

Prior to the first regularly scheduled refueling outage.

l during operation at or above 50 percent of rated ther=al power, the following surveillarice shall be per formed, in addition to that required by the Appendix A Technical i

Specifiestions and the results included in the Monthly

-t Operating Report:

a.

An overall core reactivity balance shall be compared

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to predicted values at least once every seven (7)

Effective Full Power Days (EFPD).

b.

Measured data from at least several fixed in-core detectors shall be gathered at lecst once a day. In the event of in-core detection and/or data reduction system inoperability, the time interval between measured data collections may be extended to at least once every two (2) days. !!easured data vill be analyzed at least Weekly in order to determine axial power shape and magnitude. The axial power shape and cagnitude shall be compared with the expected shape and cagnitude in order to identify any axial power distribution anomaly."

September surveillcace results are included'below:

I"T! 2.C.6.a REACTIVITY ANOMALY COP.2 AVERAGE REACTIVITY 3ALANCE DIIFERENCE DATE TI!G

, BUR':UP (EFFD)

(fEASURED - PRM)TCTED) T 9/1/78 0935 h96.15

+ 0.3

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9/7/78 0825 501.76

+03 9/15/78 0725 507.88

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ITE?! 2.C.6.b AITAL POWER SHAPE AND MACNITUDE

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CORE AVERACE AIIAL T ZR DTSTRTBITTION (?!ORMALIZED TL. ORE AVE. PWR. = 1.0) g DISTANCB FROM B0*ITOM (FT

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SEPTEM IER, 10'78 PFAK CEA GR)UP 5 MNSERTED "O 122" W ITHDRAWN 2.51 9/1/78 0812 2545.5 15,784.2 0.80 -

1.03 1.09 1.03 0.96 0.96 1.03 1.13 1.11 0.90 0.69 CEA GR )UP 5 NSERTED YO 125" W [THDRAWN PEAK 8.91 2.07 9/2/78 0812 2541.1 15,81h.9 0.83 1.07 1.12 1.05 0.97 0.05 1.02 1.00 1.07 0.87 0.66 CEA GR )UP 5 DNSERTED TO 126" k [THDRAWN 9/3/78 0809 2539.6 15,8h5.2 0.83 1.07 1.13 1.05 0.96 0.05 1.01 1.09 1.07 1.87 0.66 CEA GROUP 5 MNSERTED 00 132" W [THERAWN PEAK 8.68 2 51 9/h/78 0810 2555.4 15,876.1 0.82 1.05 1.09 1.02 0.95 0.9h 1.02 1.13 1.11 0.91 0.69 9/5/78 0810 2512.7 15,906.h 0.83 1.06 1.10, 1.02 0.94 0.9h 1.02 1.13 1.10 0.91 0.69 CEA GhoUP 5 ' NSERTED 90 121" W [THDRAWN PEAK 8.01 2.4T 9/6/78 0812 2554.6 15,936.8 0.87 1.11 1.15 1.06 0.06 0.0h 0.90 1.07 1.0T 0.86 0.65 CEA GROUP 5 1 NSERTED 9 Q 11h" W [THDRAWN PEAK 8.68 2 51 9/7/78 0807 2600.7 15,966.2 0 76 1.00 1.08 1.05 1.01 0.99 1.05 1.12 1.08 0.88 0.66 CEA GRtIUP 5 1 NSERTED 9 0 132" W [THDRAWN PEAK 2.97 2.28 9/9/78 0811 2181.3 15,994.5 0.83 1.06 1.09 1.01 0.92 0.93 1.02 1.12 1.1h 0.93 0.70 9/10/78 0810 2531.6 16,023.2 0.79

7. 01 1.06 1.00 0.95 0.05 1.04 1.14 1.16 0.07 0.71 PEAK 2.51 1.83 9/11/78 081h 253h.7 16,053.7 0.81 1.0h 1.08 1.01 0.9h 0.9h 1.03 1.15 1.12 0.92 0 70 M

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ITEM 2.C.6.h AITAT. POWER CHA!'E A:(D MAGI!ITUDE

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CORE AVERAGE AITAL T 2R DISTRIBUTTON (?!ORMALIZED Tt.ORM AVE. PWR, = 1.0) e DISTANCs FROM B0TTOM (IT )

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CEA GR0 IP 5 Ill5ERTED Tn 120" WI'FHDRAWN 8.91 2.97 s

9/12/78 0809 2018.5 16,082.7 0.88 1.11e 1.19 1.10 1.00 0.06 0.09 1.02 0.08 0.70 0.60 CEA GRO JP 5 IllSERTED Tr i 128" WI'FIIDRAWN -

9/13/78 0816 2519.9 16,110.5 0.82 1.06 1.12 1.05 0.07 0.of 1.03 1.09 1.06 0.86 0.65 CEA GRO IP 5 I lSERTED TO 129" WI FIIDRAWN PEAK 9.114 9/14/78 0809 2122.7 16,137.5 0.98

-1.25 1.28 1.12 0.96 0.02 0.03 0.96 0.93 0.75 0 57 CEA GRO IP 5 IllSERTED TO 125" WI PHDRAWN PEAK 8.68 2 51 9/15/78 0810 2h94.1 16,165.0 0.79 1.03 1.,09 1.0h 0.98 0.07 1.0h 1.12 1.09 0.88 0.67*

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• r LUlGIARY OF U:1?T_ _1__ OPERATIONS EXPLOIENCE SEPILMBER 1978 9-1 At the beginning of this report.ing period, Unit 1 was operating at 810 Ka*e.

Reactor power was limited to 953 by the Environmental Technical Specification (ETS) of 10'F limit on main condenser circulating water JL T.

9-3 Reduced load to 6h7 MWe at 20ho to investigate salt water leakage into the main condenser.

9-k Full load operation (818 Ka'e) resumed at 1100 after the salt water leak disappeared. Reactor pcwer was limited to 955 by the ETS 10*F limit on main condenser circulating water A T.

t 9-8 Reduced load to 677 MJe at 12h5 to investigate salt water leakage into the main condenser.

9-9 Full load operation (822 MWe) resumed at 2h00 after plugging two tubes.

Reactor power was limited to 96% by the ETS 10'F limit on main condenser circulating water Zh T.

9-10 Reduced Icad to 690 MWe at choo to investigate salt water leakage into the main condenser and clean main condenser circulating water tras' ^ ra' k's..

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9-11 Fall load operation (85h MWe) resumed at 0720. Reactor power was limited r to 975 by the ETS limit of 10 F on main condenser circulating water d T.

,,9-12 Reduced load to 70h tfwe at 1800 to investigate salt water leakage into the main condenser.

9-13 Resumed full load operation (8h8 MWe) at 1230 after indications of salt water leakage disappeared. Reactor power was limited to 96% by the ETS 10'F limit on main condenser circulating water di T.

9-14 Reduced load to 685 MWe at 1745 to investigate salt water leakage into the main condenser.

t

9-15 Resumed full load operation (8L7 MWe) at 1230 after plugging one tube.

Reactor power van limited to 96% ty the ETS 10*F limit on main condenser circulating water th T.

9-16 Reducea load to 705 MWe at 17h5 to investigate salt water leakage into the, main condenser.

9-17 Full load operation (861 M'a'e) resumed at 0715 after plugging one tube.

Reduced load to 705 MWe at 0820 to investigate salt water leakage into tne main condenser.

9-18 Full load' operation (865 KJe) resumed at 2130 after plugging two tubes.

Reactor power was limited to 97% by the ETS 10*F limit on main condenser circulating water di T.

9-20 Reduced load to 710 MWe at 2205 to investigate salt water leakage into the main condenser.

9-21 Full load operation (S65 MWe) resumed at 0715 after plugging one tute.

Reactor power was limited to 98% by the ETS 10*F limit on main condenser circulating water th T.

9-22 Reduced load to 700 MWe at 0500 to investigate salt water leakage into

(

the main condenser.

9-23 Full load operation (863 MWe) resumed at 0130 after plugging one tube.

Reactor power was limited to 97% by the ETS 10*F limit on main condenser circulating water o T.

9-24 Reduced load to 600 MWe at 0130 to perform mainte6ance on 12 steam generator feed pump and investigate salt water leakage inte the main condenser. Full load operatien (868 MWe) resumed at 2300 after completing maintenance on 12 steam generator feed pump and the salt water leak disappeared. Reactor power was limited to 975 by the ETS 10*F limit en main condenser circulating

- a water A T.

. 9-27 Reduced load to 718 M'4e at 0730 to investigate salt water leakage into the main concenser.

9-29 Full load operation (8L1 ffle) resumed at 2h00 after plugging two tubes.

Reactor power was limited to 97% by the ETS 10'F limit on main condenser circulating water a T.

9-30 At the end of this reportir.g period Unit I was operating at 852 IWe with I

the reactor at 95f power, power being linited by the ETs 10'F limit on main condenser circulating water A T.

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SU?C'.ARY OF UtiIT 2 OPERATITIG EXPEPIENCE SEPTEMBER 1978 9-1 At the beginning of this reporting period Unit 2 was operating at 810 Mle.

Reactor power was limited to 955 by the Environmental Technical Specification (ETS) of 10*F limit on main condenser circulating water Ji T.

9-6 Reduced load to 720 MWe at 1935 to prevent exceeding Technical Specification '

(T.S.) 3.2.6d (limit for axial shape index).

9-7 Full load operation (832 MWe) resumed at 0900. Reactor power was limited to 97% by the ETS of 10*F limit on main condenser circulating water dh T.

Commenced' reactor shut down at 1732 as required by T.S. 3 51 due to low boron concentration in two safety injection tanks. The. reactor was manually tripped at 1829 to prevent exceeding action requied by T.S. 3.0.3.

9-8 The reactor was brought critical at ik00. The unit paralled at 1510 and began increasing load to rated capacity.

9-9 Load increase was suspended at ok30 due to indications of salt water leakage into the main condenser.

9 10 Full loaa operation (809 MWe) resumed at 0015 after plugging one tube.

Reactor power was limited to 9k5 by the ETS 10 F ILsit on main condenser

,- (

circulating water di T.

9-12 Reduced load to 630 MWe at 0200 to investigate salt veter leakage into the

1. ~

main condenser. Full load operation (780 MWe) resumed at 2200 after plugging two tubes. Reactor power was limited to 93% to prevent exceeding T.S. 3.2.6.d (limit for axial shape index).

l 9-13 Reduced load to 650 MWe at 0800 to investigate salt water leakage into the main condenser. Full load operation (823 Mwe) resumed at 2200 after plugging one tube. Reactor power was limited to 975 ty the ETS 10*F limit

I

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on main condenser circulating water 21 T.

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l 9-14 Reduced load to 662 MUe at 0225 to investigate salt water leakage into l

the main condenser.

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9-15 Increase load to 809 MWe after indications of salt water leakage disappeared. Began reducing load as scheduled at 2115 to begin the first j

unit two refuelinE outage.

9-16 The unit was taken off line at 0010 and the reactor shut down. Reactor coolant system cooldown began at Ok00.

9-21 Removed the reactor vessel head at 1500.

9-26 commenced refueling operations at 1937.

9-30 At the end of this reporting period Unit 2 was shut down and in the process of replacing one third of its nuclear fuel.

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REFUELING INFORMATION REQUEST Updtted 10/ll/7Ei 1.

Name of Facility Calvert Cliffs Nuclear Power Plant, Unit No.1 2.

Scheduled date for next Refueling Shutdown.

April 1,1979 p

3 Scheduled date for restart following refueling.

May 17, 1979 k.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Resumption of operation after refueling vill require changes to Technical Specifications. The changes vill be sOch as to allow operation'of the plant with a fresh reload batch and reshuffled Core.

5 Scheduled date(s) for submitting proposed licensing action and supporting information.

February 5, 1979 6.

Important licensing considerations associated with refueling.

Reload fuel vill be similar to that reload fuel inserted into the previous cycle.

Selected fuel assemblies vill be modified by installation of sleeves in the Guide Tubes.

7 The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 2285, r'[

' Spent Fuel Pools are common to Units 1 and 2.

8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storaEe capacity that has been requested or is planned, in number of fuel assemblies.

1056 Licen~ sed 728 Current Installed 8h0 Addition is planned 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.'

Sept e=ber,198k

• • In' formation which has changed since last monthly report.

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RfFUELING INFOR*5ATION REQUEST Updated:

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l 10/11/7i s

e 1.

Name of Facility Calvert Cliffs Nuclear Power Plant, Unit No. 2 2.

Scheduled date for next Refueling Shutdown.

j; September 15, 1978 3.

Scheduled date for restart following refueling.

~

October 21, 19788*

k.

Will refueling or resumption of operation thereafter require a

~

technical specification change or other license smendment?

Resumption of operation after refueling vill require cha, er to Technical Specifications. The changes will be such as to allov s

operation of the plant with a fresh reload batch and reshuffled it Core.

A

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Scheduled date(s) for submitting proposed lice'nsing action and

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supporting information.

July 26, 1978 6.

Important licensing considerations associated with refaeling.

Reload fuel vill be similar to that reload ' fuel insert.ed into the 7

cycle 3 of Unit 1.

Selected fuel assemblies vill te'nodified by installation of sleeves in the Guide Tubes. Sixteen (16) reload fuel assemblies vill.use small guide tube hole design 7

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 I

(b) 228*, **

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' Spent Puel. Pools are Common to Units 1 and 2 8.

The present licensed spent fuel pool storage capacity and the size

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of any increase in licensed storage capacity that has been required

/

or is planned, in number of fuel assemblies.

1056 Licensed

- s s

728 Currently Installed

+

Sh0 Addition is planned

'9 The projected date-of the last refueling that can be dischargea to the spent fael pool assuming the present licensed capacity.

x l

Septemoer, 198k

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• • Information which has changed since last monthly report. >.

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SAFETY-RELATED MAINTENANCE

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I' croup MECHANICAL

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MONTH SEPTEMBER

_ YEAR 19781

+

IGLFUNCTION

..SYSTO4 OR C0!&ONE?PP MR NO. - DATE CAUSE,.

RESULT CORRJLTIVE ACTION l

1. 12 Switchgear Air -

0-77-2131,.9/1/78 Malfunction ~of solenoid Low c'ompressor suction Replaced solenoid Conditioning Com-valve (short) pressure valve pressor 1-SV-5426A l'

1. 11 H.P. MSIV 0-78-1810 6/2/78 Ruptured bladder Accumulator would not Replaced bladder.

Accumulator hold N2 pressure

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1. 11 Charging Pump.

0-78-1784 5/31/78

' Vibration fatigue Weld crack on inlet Performed weld Disch Header Relief flange repairs Valve -

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SAFE?Y-RELATED MAINTENANCE UNIT I

GROUP ELECTRICAL. I&C MONTil SEPTEMBER YEAR 1979 MALFUNCTION SYSTDI OR COMPOITENT MR NO.'- DATE CAUSE RESUL't CORRECTIVE ACTION

~

ESFAS Safety Injection 078-2209 7/8/78 Unknown B-8 16gic module tripped Replaced B-8 Actuation Signal B-8 initiating a SIAS logic module e

Module actuated alarm

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SAFETY-RELATED MAINTENANCE UNIT II GROUP ELECTRICAL, tac

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!!almi SEPTEMBER YEAR 1978 SYSTC4 OR COMPONENT MR NO.~- DATE CAUSE RESULT CORRECTIVE ACTION fil Diesel Service 0-78-2502 8/1/78 Defective solenoid Valve' stuck shut Replaced internals Water Cooler Inlet valve Would not operate of solenoid valve Control Valve 2-SV-1587 1

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I SAFETY-RELATED MAIfiTENANCE UNIT II GROUP _ MECHANICAL 3

MONTH SEPTEMBER YEAR 1978 ffALFUNCTION S'.*STDi OR COMPONENT MR NO. '- DATE CAUSE RESULT CORRECTIVE ACTION

1. 22 Switchgear Room 0-77-4168 6/15/78 Defective oil pressure Compressor did not trip Replaced oil A/C Unit Compressor regulator and oil pres-on low oil pressure, regulator and sure controller controller

1. 22 CCHX Relief Valve M-78-2326 8/2/78 Worn and corroded spring Found during surveillance Replaced spring 2-RV-5206 test and lapped seat b

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