ML18079A545

Monthly Operating Rept for June 1979

ML18079A545
Person / Time
Site:	Salem
Issue date:	07/10/1979
From:	Miller L Public Service Enterprise Group
To:
Shared Package
ML18079A544	List: ML18079A542 ML18079A545
References
NUDOCS 7907160311
Download: ML18079A545 (10)

Text

,;

AVERAGE DAILY UNIT POWER LEVEL MO:Nlli June 1979 DAY AVERAGE DAILY POWER LEVEL CM.We-NET) 1 2

3 4

5.

6 7

8 9

10.

11 12 13 14 15 16 Pg.

2 of 11 8.1-7.Rl 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 50-212 OOCKET NO. --------

UNIT Salem #1 DATE July 10,. 1979 CQ.\\-IPLETED BY L. K. Miller TELEPHONE 609-365-7000 x 507 DAY AVERAGE DAILY POWER LEVEL (MWE-NET) 17 0

18 0

19 0

20 0

21 0

22 0

23 0

24 0

25 0

26 0

27 0

28 0

29 0

30 0

31

~-

7 g 071605//.

l. trnit NaIIe:

Salem #1 Note:

2.

Beport:iJiq Period:

June 1979 *

3. Licensed 'rhemal PaEr ~):

3338

4.

Naireplate P.atinq (Gz:css l-fie) :

1135

5.

Design Electr:i.cal. P.atin9 met Miel:

1090

6.

MaxiimJm r:ependable Capacity (Gz:css. M'le) :_l..;;l;...2..;;4 ____ _

7.

Maxiim.m* Dependabl.e capacity* (Net !.fie) : __

1_07_9 ____ _

rx:cKET ro. :_5_0_"-_2_1_2 _____ _

CATE :

July 10, 1979 COMPLETED BY:

L~ K. Miller TElll'B:NE: 609-365-7000 X507

a. If Olanges Occur in Capacity P.atings (Item NIJl!Cer 3 ~

7) Since Last Ret:lert, Give Reason:

NONE

9.

Pcr.ler* Level Tc Which Psstrie'"..ed, If Aey (Net Mtle) : ______

N_O_NE ___________ _... ____ _

10.

Reasons For Restricticns,- If Mr;/:

• NONE This M:nth Year to Date Ctmllative ll. ECurs In ReE:ortin9' PericXl 720 4,343 '

17,544

12.

NulrCer Of ECurs P.eactor Was Critical 0

2,184.5.,

9,841.4

13. Reactor Reserve Shutdown Iburs 0

22.7 22.7

14.

Hours Generator On-tine.

0 2,161.3 9,459.3 IS. Unit P.eserve Shutdown Hours 0

0 0

16.

Gress TheJ::mal. Energy Generated (!-Ml) 0 6,482,491 27,467,227.

17.

Gress El.ect:rical. Energy Generated (MWH)

• 0 2,181, 770 9,154,580

18.

Net Electrical Energy Generated (M>IH)

(2,628) 2,079,279 8,666,259

19. O'nit Sel:vice Factor 49.8 53.9

20.

O'nit Availability Factor 0

49.8 53.9

21. O'nit Capacity Factor (Usinq MOC Net) 0 44.4 45.8

22. O'nit Capacity Factor (Using DER Net) 0 43.9 45.3

23.

O'nit Forced Outage Pate 0

3.0 31.3

24.

ShutCa.ms Scheduled Over Next 6 Months (Type, Date, arid Duration of Each) :

NONE

25. If Shut eown At Er.do£ P.eport Period! Estimated Date of startup: ___

A_u_gus

__ t_8_,_1_9_7_9 _______ _

26.

O'nits In Test Status (Prior to Camercial Cperation):

8-l-7.R2 Pg. 3 Of 11 Forecast 9/30/76 11/1/76 12/20/76 Achieved 12/11/76 12/25/76 6/30/77

00.

DATE 79-189 4/3/79 1

F:

Forced S: Scheduled Page 4 of 11 8-1-7.Rl TYP~

s 2

UNIT smmxims l\\ND PrnER REriCTIONS REPORr MJm'll June 1979 Mfilll)I)

OF

~

WW\\TION

.~

s1nnT.roo LICEmt SYSTEM (llXJRS) ram EvENr

<XJDE4

<XJDE~.

REAC'IDR nEroRr. I DOCKET NO. : __

s_o_-2_1_2 ____ _

• UNIT *NAME:

Salem #1 DATE:

July 10 1 1979 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 CAUSE AND aJRROCTIVE ACTION 'ID PREVENI' REL'lJlmENCE 720 c

1 RC FUELlQ{

ANNUAL REFUELING OUTAGE.

Reason:

A-D;Juipoont Faiiure(Explain)

B-Maintenance or Test C-Refueling D-Regul.atory itestriction E-cperator Training & Lioonse EKandnatit>n r-lldministrative G-q>erational Error(Explain)

II-other (Explain) j 4

~thod:

1-Manual 2-Manual Scram.

3-Aut:aoatic Scram.

4-other (Explain)

A.

LOAD REDUCTION B.

CONTINUATION OF PREVIOUS OUTAGE.

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (UR) File (NIJREI}-0161) 5 Exhibit 1-Sam!

Source

- MAJOR PLANT MODIFICATtts REPORT MONTH June 1979

• DCR NO.

PRINCIPLE SYSTEM lEC-0579 Fuel Handling lEC-0582 Fuel Handling lEC-0589 Fuel Handling lPD-0154 Main Steam

.. lSC-_0148-13 Component Cooling lST-0180 Fuel Handling

• DESIGN CHANGE REQUEST 8-l-7 Rl DOCKET NO.:

UNIT -*1E:

50-272 Salem #1 DATE:

July 10, 1979 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 SUBJECT Replace Manipulator Crane Sleeve Bearings Manufacture special RCC Handling Tool Manufacture special RCC Handling Ba.sket Insulate South Penetration Tubing Trays Replace internals in 13 Componen Cooling Pump Manufacture temporary RCC Change Fixture Page 5 of 11

DOCKET NO.:

50-272

~~~~~~~~~~-

?~OR PLANT MODIFICATI(jii REPORT MONTH JuB._e 19~

UN IT ~: Salem #1 DATE:

July 10, 1979

• DCR NO.

lEC-0579

• lEC-0582 lEC-0589 lPD-0154 lSC-0148-13 lST-0180 COMPLETED -BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 10CFRS0.59.

SAFETY EVALUATION This design change is made to reduce maintenance and increase efficiency of the manipulator crane sheaves.

This change will not result in a change to the SAR's and an unreviewed safety question is not involved.

The handling tool to be manufactured as a result of imple-mentation of this DCR is for temporary use only and is not considered as permanent plant equipment.

The application for which this tool is intended is in no way pertinent to a safe shutdown of the plant.

Based on the above enactment of this DCR,. *it does not constitute an unreviewed safety question nor would it result in a required change to the SAR.

The equipment to be manufactured as a result of implementation of this DCR is intended for temp9rary use only and is not considered as permanent plant equipment.

The service for which this equipment is intended is not pertinent. to a safe shutdown of the plant.

Enactment of this DCR does not constitute an unreviewed safety question nor would it result in a required cha.nge to the SAR.

This is not a safety related change and does not directly affect safety related equipment.

This is a request for freeze protection by means of insulation.

This change will allow safety related instruments to operatec.1as intended.

Safety analyses are not altered.

The alternate change in material from carbon steel (and hard chromecs~eei) to 316 stainless steel does not present an unreviewed safety question as the functionability remains the same.

The temporary RCC change fixture fabricated in accordance with this DCR does not pose an unreviewed safety question as this tool does not affect safety related systems or the safe shutdown of the plant.

Page 6 of 11

DOCKET NO.:

50-272

SUMMARY

OF SAFETY RELATED ~NTENANCE

-~------------'

UNIT N-- : __

s_a_l_e_m_#_l ______ _

DEPARTMENT Maintenance DATE:

July 10, 1979

---

~~--

REPORT MONTH Jufue 1979 CO MP LET ED BY:

L. K. Miller

---

~~--

TELEPHONE:

609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

010680 Valve, 10WG036 Sticks.

Disassembled, Cleaned, Reassembled.

901669

.Motor, 16 Service Remove.MJtor for repair.

Removed motor, replaced with Water Pump.

spare.

901721 Pipe, 15 Service Exjsting spool piece Replaced with new spool piece.

Water Discharge eroded, corroded.

Spool Piece.

Q01722 Pipe, 16 Service Existing spool piece Replaced with new spool piece.

Water Discharge eroded, corroded.

Spool Piece.

~.901763 Uni ti:;>,. 11,, :12, 13,

Machine 45 Degree Bevel Machined plate.

and ll'.4.cJ?an CoiL __ on Pillow Block Bearing Plate.

902867 JYbtor, 12 Service Excessive Noise.

Replaced.Bear.lng, repaired Water Pump.

motor bearing cooler.

902887 Supports, 11, 12, Provide Level 1 Machinist Hot/Cold Support Position 13 and 14 Steam for Hot/Cold Snubber Readings taken.

Generator Snubber. Position Readings.

902920 Air lock, 100' El.

Replace defective cam Replaced cam followers.

Containment.

foll0wer.

903174 Filters, 11, 12, Filters rEqUire changing.

Filters replaced.

and 13 Aux. Bldg.

Hepa.

903542 Valve, 13MS010.

Repack.

Repacked.

903795 Pump, 11 Charging Install temporary Completed.

demineralized water supply I

to pump seal cooler during component** cooling water I

I outage.

I I

Page 7 of ll:i

DOCKET N0.: __ 5_0_-_2_72 ______________ _

S~MMAR~- OF SAFETY RELATED ~TENANCE DEPARTMENT Maintenance UNIT N. __

s;;..;al~em;;;;....#::.;;l;...._ _____ _

DATE: __

J_u_l..;;;;.y __

1_0_, __

1_9_7_9 _____ _

REPORT MONTH_~J_un~e~l-97_9 ____ __

COMPLETED BY: ___ L __

._K_._Mi~*.1_1_er

__ ~~------',

TELEPHONE: __ 6_0_9_-_36_5_-_7_oo_o __ x_5_0_7 ____ _

WORK ORDER NO.

903834 905647 905937 905939 905947 EQUIPMENT FAILURE DESCRIP~ION Pl.;rrnp, 16 Serv. Wtr Vibration.

Annunciator, Aux. Typewriter.

Typing erratic.

Valves, 12.MS113, Repack, Replace oonnet 12.MS114.

gaskets.

Valves, 12MS090, 12MS117.

El:ectrical Penetration, 1-03; 1~15, 1-13.

Repack, Replace bonnet gaskets.

IDwNi.tr0gen Pressure.

CORRECTIVE ACTION Replaced Motor.

Replaced printed circuit board.

Repacked, Bonnet Gaskets.

I replaced.

Repacked, Bonnet Gaskets replaced.

Repressurized, No leaks found.

'----~---+~~~----~4-----~-~--~----1--~-~~~~---~--~1-8 of 11

DOCKET NO. :

50-272

~--------------------~

UNIT N4: __ s_a_1ern

___ #_1 ______________ _

SU~Y,OF SAFETY RELATED ~TENANCE DEPARTMENT ____ P_e_r_fo_rman c_e ____ ~

REPORT MONTH June 1979 DATE: July 10, 1979 COMPLETED BY: L. K. Miller

~----------------------

TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

904331 Instrurrent, out of Calibration.

Calibrated.

lLTOl.12~

904742 Valve Operator, Ground on Control Circuit.

Replaced defective solenoid 20PR001.

Valve.

904893 Instrurrent, I'.,

out of Ca.libration<

Replaced Strain. Gauqe,

• 1LT0114.

Calibrated.

• Page I*

9 of 11

SALEM UNIT I OPERA.TING

SUMMARY

JUNE 1Q79 6-1 thru 6-30 REFUELING OUTAGE.

Page 10 of 11

-REFUELING INFORMATION e MONTH:

June 1979

~----------------------

50-272 DOCKET NO.: --

UNIT: Salem #1 DATE: July 1.0, 1979..

COMPLETED BY: L. K. Miller.

TELEPHONE: 609-365-7000 X507

1.

Refueling information has changed_from last month:

YES NO X

2.

Scheduled date of next* refueling:

March 29, 1980

3.

Scheduled date. for restart' following refueling:

May 25, 1980

4.

A.

Wil.l Technical Specification changes or other. license amendments be required'?

YES NO ---

NOT DETERMINED TO-DATE June 1979 B-.. -- *Has the-reload.fue*l. -design. been reviewed. by the Station. Op_e:t;ating Review Committee?

YES NO x

If no; when is it scheduled?

February 1980

5.

Scheduled date(s) for submitting proposed licensing action:

February 1980 (If ReguireqJ_

6.

Important licensing considerations associated with refueling:

None

7.

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Fuel Storage*

0

8.

Present licensed spent fuel storage capacity:

264 Future spent fuel storage capacity:

1~170

9.

Da.te of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Page 11 of 11 8-l-7.R4

• April 1982