Text

Monthly Operating Rept for Jan 1980
	ML18081B051
Person / Time
Site:	Salem
Issue date:	02/11/1980
From:	Miller L; Public Service Enterprise Group
To:	;
Shared Package
ML18081B050	List: ML18081B049; ML18081B051;
References
	NUDOCS 8002150270
	Download: ML18081B051 (53)
	v • d • e

MONTH January 1980 DAY AVERAGE DAILY POWER LEVEL 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 Pg.

2 of 18 8.1-7.Rl (MWe-NET)

342 319 369 370 515 598 507 763 788 980 1,100 908 1,023 299 0

630 A VERA.GE DAI LY UN IT PO\\'iER. LEVEL OOCKET KO. 50-272 UNIT Salem #1 DATE February 11, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 x 507 DAY AVERA.GE DAILY POWER LEVEL (MWE-NET) 17 924 18 943 19 1,047 20 833 21 1,069 22 1,092 23 379 24 96 25 856 26 1,069 27 1,084 28 1,021 29 1,048 30 1,114 31 1,114

l. Unit Nane: ____ s_a_l_e_m_#_l ________ _

2.

Reporting Period: ___

J_a__._n..

u.... a=r._.y___...1--..9.... 8.... 0 ____ _

3. Licensed '1betlnal PolEr (KVt) : __...,3..,3_3...... 8 ____ _

4.

Naneplate Rating (Gross.!4'el : ___ 1_1_,3,,...5,,..,,..-=-----

s.

Design Electrical Rating (Net.!4'e): __ 1_0_9 __ 0 ___ _

6.

Max:i..mm Dependable Capacity "(Gross~) : __

1_1_2_4 __

7.

Maxilllllm Dependable capacity (Net~): __ l........ 0.... 7.... 9 __

Notes:

50-272

~NJ.: ________

DATE:

February 11, 1980 o:M'I.ErEDBY: L. K. Miller

'rEIEl?lDlE: 365-7000 X507

8. If Changes Occur in Capacity Ratings (Items NlJll'Cer 3 'n1rcu;h 7) Since Last Report, Give Reason:

NONE

9.

Power Level To Which Restricted, If Arr:! (Net z.tVel : ______

N_O_N_E ____________ _

lO.

Reasons For Restrictions, If Aey: __

_N_o_N_E ______________________ _

'1his M:Jnth Year to Date Cunnllati ve 744 744 22,705 ll. Hours In Reporting-Period

12.

NlmtJer Of Hours Reactor Was Critical 696.4 696.4 10,784.4 l3. React:cr Reserve Shuta:Jwn a:iurs 0

0 22.7

14.

Hours Generator On-Line.

681. 7 681. 7 10,212.8

15. Unit Reserve Shutdown Hours 0

0 0

l6. Gress nlel:JMl Energy Generated (mH) 1,789,716 Li.789, 716 29,326,013

17.

Gross Electrical Energy Generated~)

586,080 586,080 9~753;580

18. Net Electrical Energy Generated(MWH) 556,282 556,282 9,185,872

19. Unit Service Factor

91. 6

91. 6 45.0

20.

Unit Avaj 1 ahi Ji ty Factor

91. 6

91. 6 45.0

21. Unit capacity Factor (Using MOC Net) 69.3 69.3 37.5

22. Unit capacity Factor (Using DER Net) 68.6 68.6 37.1

23. Unit Forced Outage Rate 8.4 8.4 43.4

24.

Shut:dcwns Scbedul.ed Over Next 6 Mc:nths (Type, Date, and Duration of F.a.ch):

NONE

25. If Shut Down At End of Report Periodr Estimated Date of Startllp: _____

N_/_A __________ _

26. Units In Test Status (Prior to camexcial. ~tion) :

8-l-7.R2 Pg.

3 of 18 Forecast 9/'.30/76 11/1/76 12/20/76 Achieved 12/11/76 12/25/76 6/20/77

NJ.80-001

.80-002 80-003 80-004 80-005 80-009 80-015 80-017 80-019 1

DATE 1/1/80 1/3/80 1/5/80 1/7/80 1/8/80 1/11/80 1/14/80 1/17/80 1/20/80 F: Forced s: Scheduled Page 4 of 18 8-1-7.Rl TYP~

F F

F 2

UNIT Sln.JTIU'INS l\\ND lER RE!Xx:rIONS REPORI' ID!mt January 1980 METIDD OF OOMTIOO

~

SllUITl~

(IDJRS) ro'IN REACTOR 0

D 5

0 D

5 0

D 5

0 D

5 0

D 5

0 A

5 37.1 A

3 0

A 5

0 A

5 Reason:

A-B:)ui~t Failure(Explain)

B-Maintenance or Test C-Fefueling O-Fegulatory Restriction LICENSE EVEN.I' REPORI' I E-operator Training & License Examination F-.Administrative G-<lJerational Error(Explain)

H-other (Explain)

SYSTEM ~

CODE4 CODES SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz HH HT EX CH RB zzzzzz HH HTEXCH HH HTEXCH 3

~thod:

1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO.:

50-272 UNIT*NAME:

Salem fll DATE:

February 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 Cl\\.USE 1\\ND CORROCTIVE ACTION 'IO PREVml' REDJRREN::E NRC Tech. Specs./Reg. Guides NRC Tech. Specs. /Reg.*

Guides NRC Tech. Specs./Reg. Guides NRC Tech. Specs. /Reg. Guides NRC Tech. Specs./Reg. Guides Clean Condensate Pumps Suction Strainers Nuclear Instrumentation (Spurious noise spide on Power Range Channel N-43 while N-44 was in test).

Clean Condensate Pumps Suction Strainers Clean Condensate Pumps Suction Strainers 4

5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NURm-0161)

Exhibit !-Same Source X507.

oo.80-022 80-024 80-026 DATE 1/23/80 1/23/80 1/27/80 Page 5 of 18 8-1-7.Rl TYPE1 F

F F

OORl\\TIOO REASON2 (IJ.:XJRS) 0 A

25.2 A

0 A

UNIT SllU'l1U'INS 1\\ND POOER RIDX:l'IOOS REl'ORI'MJNI'H January 1980 MlmlJD OF smrrr100 LICENSE SYSTJ:M CDII'CMNl' l:OIN EVEN!'

OJDE4 OJDE5 RFJ\\CIDR REPORI' I 5

HH HTEXCH 3

HH TRAN SF 5

HH HTEXCH 50-272 DOCKET NO.: ----..,,.----

UN IT *NAME:

SaJ.§m ffl DATEI February 11~ 1980 COMPLETED BY: _L_._K_._,,..,M.,..1_* 1_1_e_r __ _

TELEPHONE:

609-365-7000 X.S.07 CAUSE J\\tll CDRROCTIVE ACTION 'ID PREVENI' RB:URREN:E Clean Condensate Pumps Suction Strainers Loss of Auxiliary Transformer Clean Condensate Pump? Suction Strainers

MAJOR PLANT MODIFICATIO.

.REPORT MONTH January 19

DCR NO.

PRINCIPLE SYSTEM lED-0191 Sampling lED-0343 Cathodic Protection lEC-0438 Circulating Water lEC-0465 Control Air lEC-0561 Main Turbine Lube Oil lEC-0568 Fire Protection lEC-0623 lEC-0678 lEC-0683 lEC-0699 lMD-0051 lPD-0037 lSC-0018 lSC-0025 lSC-0046 lSC-0064 lSC-0112 MSIV Containment Ventilation 4KV Vital Busses Containment Sump Reactor Head Aux. Temperature Indication Communications Fuel Handling Fire Protection Overhead Annunciator Control Room

DESIGN CHANGE REQUEST 8-1-7.Rl DOCKET NO.:

50-272 UNIT N~ Salem Ill DATE:

February 11, 1980 COMPLETED BY:

L. K. Miller TELEPHONE:

609.:...365-7000 X507 SUBJECT Install Feedwater o2 Analyzer Install Ground Beds at S.W. Structure Modify Controls for Manual Operation Remove and Replace Piping fcir Condenser Retubing Install Lube Oil Filter Install Additional Aux. Building Hose Reel Remove Overload Jumpers on Hydraulic Pump Modify 1VC5 & 6 to Improve Operation Change. Relay Setting Install Vortex Baffles and Reset Level Switches Modify Themocouple Trays Replace Bristol Recorders with the

'Do-ric Install S.P. Phone at Pressurizer Modify Fuel Transfer System in Accordance With Westinghouse WRAPS f ackage Replace HP Turbine Fire Detector Modify Alarm Windows D-37 and D-45 Install Improved Clock Page 6 of 18

50-272 MAJOR PLANT MODIFICATI~

REPORT MONTH January 1980 DOCKE~~*:

UNIT DATE:

Unit Ill February 11, 1980

DCR NO.

lED-0191 lED-0343 lEC-0438 lEC-0465 lEC-0561 lEC-0568 lEC-0623 lEC-0678 lEC-0683 lEC-0699 lMD-0051 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 10CFRS0.59.

SAFETY EVALUATION This change is not safety related and does not affect safety related equipment.

X507 This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unreviewed safety question per 10CFR 50.59.

This system is not safety related.

The change increases the flexibility of operation without impairing reliability.

The type of materials employed il'Lthis_.. change are identio.al to those used in the current design.

This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Technical Specifications are not affected.

This design change will not require a change to the Tech. Specs. or FSAR.

The additional filter equipment nor the surrounding equipment is safety related.

This modification will improve the main turbine lube oil

~leanliness and increase reliability.

The* installation of the hose station required by this DCR has been previously reviewed and it has been found that it does not present an--

unresolved safety question.

No additional fire :hazard is introduced by the addition... of this hose station.

It improves the plant safety features against fire.

The modification does not change the functional operation of the system nor degrade its performance.

The reworked valves will not adversely affect existing safety equipment or invalidate existing safety analysis.

This design change will assure that the valve closes when required to.

This change does not alter the functional design of the system.

It reflects preferred method of applying protective relays.

The existing design was necessary only because seismic data on preferred design was not previously available.

No modifications affecting fire systems are made.

Implementation of this DCR will insure a safer shutdown of the NSSS equip-ment following an accident involving a breach in the primary coolant system by providing anti-vortex baffles in the reactor building sump pit on the suction side of the residual heat removal pumps.

Modifying the two cable trays does not involve any safety questions.

DESIGN CHANGE REQUEST Page 7 of 18

50-272 MAJOR PLANT MODIFICATI~

REPORT MONTH January 1980 DOCKET Jik. :

UNIT N DATE:

Salem 111 February 11, 1980

OCR NO.

lPD-0037 lSC-0018 lSC-0025 lSC-0046 lSC-0064 lSC-0112 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 10CFRSO. 59.

SAFETY EVALUATION The system and instruments involved in this change are not safety related but the instruments are mounted in a Class I cabinet (lRPl).

Class I cabinet requirements have been considered for lRPl and have not been altered by this change.

This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unresolved safety question per 10CFR 50.59.

This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Tech. Specs.

are not affected.

This is not a safety related system and has no effect upon the safe shut-down capability of the plant.

This change is not functionally safety related and supports a design analysis revising the alarms so that the alarm windows remain "black" unless both the reactor power is above 50% and the quadrant power tilt ration exceeds 1.02. It is classified as safety related because the work performed will be in a safety related cabinet.

This design change is not safety related and does not affect any safety related systems or the safe shutdown of the unit.

DESIGN CHANGE REQUEST Page 8 of 18

(.

Si1LEH GEi'IERr'1Tii-.JG STr'lTIOi'l

]'

L iiONTHLY REPOl:rf OF Sr'1FET't' REU!TE[I r~EPrHRS 0001 WORI\\

D(.1TE PROBLEii DESCRIPTION DrHE DESCRIPTION OF REPAIR r*

1 Q.,,R""D,..E_._,R __

... w._.R...._I_,__T_,__T..._Eu.N_______________________

. _____ COMF.:LE..TED ____ -----*--------------"------- -

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--*----- *------------~--

*--*------**-- -. ---* *--** -------------------~-:

_________ "i I 8

- - MAINTENANCE DEPARTMENT WORI\\ ***

__ J,\\

_1::1!

f-1 ___________________

13j 900236

~ "I 15 1

"f---9-0_0_6

__ -..,--1-2_1_6_7_8 __________

V_r:'.iLVE ll5.Jl43 Hf°1S F'ACl\\ING LEf°11\\

04 l.L 79 REPf'.1CKED

(;

., ::.I

. :~ 12::

03 21 79 WtLY..E..___ljj:jS167 REE'(..JCI\\

0.5_l_0_7_9 ______ __.REP.i!.k1'.ED II 1::

19~~~-~~-~~---------LL"-

12

1 901366 04 14 79 VALVE 12GM REWORI\\

04 15 79 iir'..iCHINED DISC AND SE(lT

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___ Ji'lSTiil I ED rJEW Gi>Sl\\EIS REPr-'.1CKED

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~;11 21 90.l.6~1 ~9-~0=4_3..._1,..j_7~9~----------"'V1lLJ.IE._l_3ii5 I I REW.0.~*~* ____________ 0.5_24_29-_________ D I.s1:1s_s.E.rill~~----------

251 Lr-'.1PPED

--11*"

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r*~SSEMBLED

)

1 1

~~1L901620 O*I 30 79 Vf.1LVE 13ii512 REWORK 05 23 79

~~~~'.~~EiiBLED

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(1SSEMBil""'D'-------------

31 I"*

) :

901621 04 30 79 VALVE 13M513 REWORK 05 29 79 Disr:1sSEHBLED j;;

l<

--------~~~i~l-.E-_[_I __________

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(I I~}

09 14 79 FLANGE LEAK NEAR VALVE 115W223 10 02 79 WELD REPAIRED PIPE AND APPLIED BELZONA COATING

1---=L.,Uu:;..;;,__--"t.:i._~~.z__ _______

___)i~LVE 13ii51*1 REW.0,_,*..... *------------.3'-'5_2_9_J9

__rrI.SJ'.1SS.E.ii.Itl..E~D _________ _

Lr'*1PPED

ASSEi*iBLED

)

311 3*1 1'

0 901623 0*1 30 79 Vf.1LVE 13ii515 REWORK 05 30 79 DISr'1SSEiiBLED Ai*

) "

U1F'F'ED W'

~, *

___ i1SSEiiBL...

...,l ___________ -,----1' I J ::c:*

901629 03 21 79 VALVE l2M5167 REPACK 05 10 79 REPACKED

---i~I 901_6_3_0 __

0_3_2_1_7_9 _________

V_r-i_L_V_E_.L __ 3_i*-iS_l_6_7--R-*E_F_'fi_C_I,-. ------------Q5*1*0--7-9-----------R-EF'r:1cKED e

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05 __ !_O __ J_<2 ______

~REf".(tCJ\\._..,_1 _______________ ~H

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.... 7_-_19_____

WiLVE ll5.J34 LE1:11\\S THRU

-- ------------- _____ v_*~--~~~--:.~------

_____ '-_~_o_~-~=~EI~-~~-i-.JG_,_ER_*_B_o_L_T ______.

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902801 04 ll 79 VALVE 14GB4 FAILED LEAK RATE TEST 04 16 79 MACHINED DISC i SEAT

~,

I,~

INST1:1LL.ED NEW GFiSKETS

) :r------------------------------------------------------BEE'r'1kJi.E,,,,.I"'-*1 _____________ _,

1

'.i.

__ _,.j Page 9 of 18

\\ L--=~-=c.==-

~~***----*----------- ---------- ---------*- --**----------

SALEH GENERATING STATION MONTHLY REPORT OF SAFETY RELATED REPAIRS

)

WORK PROBLEii t'il:'.SCfUF'TION DA7E"

~1-----"-'"U.J.J'---""'"'-.Ll-J-J-J"-------------------------------_,_,_*,oiiPLEIEIL. __ _

-- ~

0002 DESCRIPTION OF REPAIR 1

1 5

. I' REPLr.:icED *-B-ON_N_E_l_' _S_E_(l-L--~----------1~,*

REPFiCKED

. I'.,

903061 04 21 79 VALVE 14AF23 HAS PACKING LEAK 12 OB 79

) :1

-,,:I

)

11 12 903829 905924 02 26 79 07 03 79 16 SERVICE WATER PUMP INSPECT & REPF'1IR VALVE 1SW22~ BINDING 131 ___

9_1_3_7_3_9 __ 1_0_2_7_7_9 _________

J-.A-[-1I_E_S_E_l_-G_E_N_E_R_A_T_O_R_E_X_H_r:.iu_s_i _____..

\\

M MANIFOLD LEAKS 16

)

17 914344 "1-_

_,_ti.345 I~

)

20 11 15 79 VALVE 11MS45 HAS PACKING LEAK 11 J 5 79 VALVE 12fi.EZLl::l1JS P(1CKlrlli_LE:B..,.K __

03 o5,_7_9 ____..... ***------~~-~ ~~s~;:~~~i~~ ~~~[l~R* FOR*~~~~--------i::1-

---RE-POSITIONED BELL CRr~i'-IK

--- ----l::i 08 21 79 REPrKKED i I

. ---* ---*---- ------- I_N_S_T_A_L_L_E_D_N_E_W_G_A_S_K-'E_T_S ________ -*- - -1::1 l.2-0L.Z9 ________

REF~A.C.KE.D

.REPLACEb BONNET SEAL

_____ !_2 07..7.9. ________ REl:'E!CKl;J.~' ---*------

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.. ---1;:

1:- (

9!::1 1

I*:: (I

1'.:

914349 11 15. 79 VALVE 14MS.L30 Hf'.15 PACl\\ING LEAK REPF"_1c_K_'E_r_1 ________________ !.=: (1

)

~

914391 12 31 79 11 CHILLED WATER PUMP RUNNING HOT 01 01 80 REPLACED BEARINGS 1

~

1 ci

~--~~1~4~4~1~7 __

0_1_0=3~8~-------~~~~li~~EAKING

______ OLO~~-------RE~LACEQ~~A~~L-------l:,

REPLACED OIL SEALS J

) ni

1c l:.il ___ 9.lA.4.5_6_~0-1~0~4~9*--------~~Cl:l.IL I ED Wli.IEfLf:'.U11f' TR I PP INli__ __________ fJ l _05_a.u_ ___________ REf'Lr-iCEILllilERJ..J:lr:it~1S~---

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> 1::1, ____ 9_~~~74 01 14 80 VALVE 11SW24 F_1 __ A_N_G_'E_L_E_r:_1K_' ---~-----*----* _01 -~~-~-~- --- - --** -----=-~~~~-L_L_E_D_N_E __ w_v_f~_Lv_E_B_o_r_,.( __

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915871 08 15 79 VALVE 1RH26 HAS PACKING LEAK 08 17 79 REPACKED

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-rl

~~

1t 915878 08 15 79

~AL.YE.i.1.BJ:!~_Q_H.AJLPA.CKJ..NG_!,..E;J)l\\ _________ 08_17 __ zy_ ___________ REf~(tCr;J;D__________

.! ~:,:---~1-5880 08 15 79 VALVE l1RH:L8 Hf)S PACKING LEiiK 08.L7 79 REPl1Cl\\ED

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916090 12 13 79 VALV_E_* _1_4";-_:i-F~2-*-l~~L-~Ef~)K~*s~~T~HR-*-~~-------~-==------.-===-~ l~--l-~:*7~~--~----~-----------~~~-~t~~~DF~~ ~~~~~~E---------- *----_-_____

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916092 12 14 79 VALVE :L.L1-)F2l LEr'.iKS THR-U-----*------*- ------~~ ~~:9_.....

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~I 917436 11 06 79 VALVE 13SW264 LEAKS THRU 11 22 79 REPLACED DIAPHRAGM

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J ___ 9_1.'Z.502 11 1J 79

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. ___ REF.'.LACED.F...ILTERS ___________________,.

1

~1 ROUGHING FILTERS DIRT'(

i;: l

L ____ ~J]l)63 11 15 79

____ 1_4__ CD~.TAHlii_E_NLE!:W_S_OIL ________________ --** 11. 26 79

__ REPL1~CEQ_J."J.LIER.S ______ --- --*-. --- --

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~1 ROUGHING FILTERS DIRTY j

1:.. 1,.

PUMP START LIGHT DOES ON VALVES lH5132 AND 1HS52 I~ I

~:1, ___ 9_19_a_Ql 01 16 80

_13 __ {:\\U)(I_L!1)R_'.( _F:EE))WrHEl't_ _______ **- -----... Ol _.17 _80 __ -*

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NOT LIGHT I ___ ----*---

Page.10 of 18

r Sr~LEM GEi*lERrHii'ff-, -S-Tr-"-11-'ION ________, _____ ------------------------~

b MONTHLY REPORT OF SAFETY RELATED REPAIRS 0003 j---~~~-~-~~*-~W~R~*~~~~~~~~N~ __________

P_R_*o_B_L_E_M_D_E_s_c_R_I_PT_Io_i_~---------~~~-----~CRIPT:_[O_N_o_F_R_E_P_A_I_R _______ f

,r 919398 VALVE.L2iiS.L68 HAS PACh:ING LEr.'.iK

,, __, -----1*2-*05-79* *-----**-** -------RE*F*~)c_K_"E_D___

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~--* : _ _99.1199~45!5~90-~~~~--------VALVE..:.1AH5..L6_8__J:tA5-:E'ACK.I.NILLEi~K-----------_L2 __ 06.. 79. -. - --- --. ___ PEF'.f~CKE-D__________ _ __ "!:"_

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VALVE lPS2 HAS BROKEN REACH 11 28 79 REPAIRED REACH ROD

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9_1_9_4_6_4 _____________ -l'.\\,v:~L-VE--12-.s-.J-4_o_H_A_S_F_'A_c_K-.I-N_G_L_E_A_K---------*--1~--~a---79

_____ ------- ------;~-F~f~CKED

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-, ::1 919539 11° BORIC f°lCID TRr.'.!NSFER F'UMP

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SEAL LEAKING

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---DRAI_N_E_D_O_I_L

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I VITAL HEAT TRACING 12 26 79 REPAIRED

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---- '::.i 919593 12 21 79 919676 VALVE 14MS18 HAS PACKING LEAK 9:L9681 VALVE 14AF23 HAS PACKING LEAK Page 11 of 18 12 27 79

'.-u 17 79 11 21 79 11 22 79

.L.L 17 79 l.I.

~.I. 79 1**',

-------------- ('/

"i l*!it REPAIRED HEfH TAPE INSTALLED NEW CUNOSEAL j

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REPfiCKED I

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---~ -.REP{~CKED _____________________ _

REPr'.'iCKED REPr)CKED

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32 919784 12 06 12 06 1? 06 12 06 12 17 12 22 12 23 12 27 12 27 Page 12 of 18 79 79 79 79 79 79 79 79 79

--i:>Hl=t>n--l7t:,~l~f~Hlll~l3 -bll--ll-!UI~---- ----

MONTHLY REPORT OF SAFETY RELATED REPAIRS PROBLEM DESCRIPTION VALVE 11MS168 HAS PACKING LEAK DrHE COMPLETED 12 07 79 0004 DESCRIPTION OF REPAIR REPACl\\ED

-, r MONTHLY REPORT OF SAFETY RELATED REPAIRS 0005

*--*-------------]

DATE DESCRIPTION OF REPAIR COMPLETED r.. 1

~----------ii PROBLEM DESCRIPTION

~

WORK DATE

~

ORDER WRITTEN

-~~~~~-'~--------~l~::>~F_UELHtlNI1LI.J'LlLBUI.LitI.NG. ______________ l.2_2_9_Z.9 _____________ REF~Lf'.lCEIL.BROb:EN BELTS

-1' ~,-*I.

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SALEM UNIT #i OPERATING

SUMMARY

JANUARY 1980 1/1 At 40% power, steady state conditions for entire day.

1/2 At 0330, commenced inserting rods by dilution to 140 steps to swing 6I negative in preparation for a flux map.

Power remained at 40% for the whole day.

1/3 At 0500 on 1/3/80, waiting for 6I to stabilize for power coefficient test.

Between 0640 and 0740, turbine load being increased then decreased.

At 0750, commenced increasing power to 47% at 3% per hour.

The reactor remained at 47% for the remainder of the day.

1/4 1/5 thru 1/6 1/7 thru 1/8 Power remained at 47% for the entire day.

Power being increased from 48% to 60% on 1/5/80 in preparation for next physics test.

Once physics test was complete, power was reduced to 50% by 2400 on 1/6/80 to clean feed pump strainers and to evaluate quadrant power tilt.

Power remained at 50% until authorization was given to go to BO%.

At 2200 on 1/7/80, power escalation began at approximately 3% per hour.

Power was held at 80% for physics testing.

At 2115 on 1/8/80, reactor power reduction began from 80% to 65% power to clean condensate pump strainers.

1/9 At 1200 on 1/9/80, power escalation began at 1.5% per hour to 95% which thru 1/10 is the next physics testing plateau.

Power remained at 95% through 1/10 while physics testing was in progress.

1/11 Still performing physics testing.

At 0630 on 1/11/80, commenced power thru 1/12 Page 15 of 18 reduction at 3% per hour down to 70% to clean condensate pump strainers.

At 2100, with strainers cleaned, power escalation began at 3% per hour reactor thermal power.

Power remained at 95% for the remainder of this period.

1113 1/14 1/16 1/17 1/18 1/19 1/20 1/21 1/22 Page 16 of 18 At 95% power until 1400 when load reduction in order to perform governor valve closure of #12 stop valve was commenced.

Load reduction terminated at 93% power and remained there for the remainder of the day.

Power escalated from 93% to 95%.

At 0956 on 1/14/80, reactor tripped from 95% on a false high neutron flux rate trip signal.

Reactor remained subcritical until 1013 on 1/15/80 when reactor was taken critical.

Remained at zero power until reactor tripped at 1630 on steam generator low low level.

Reactor brought critical until it tripped again at 1900 on steam generator low low level.

Reactor brought critical and power escalation began.

At 2400 on 1/15/80, power was 18.2%.

Power escalation continued.

At 1234, experienced turbine load swing due to E.H. control system malfunction.

Turbine placed in manual.

At 2400, reactor power was at 89.5%.

Power reached 95% at 0400.

At 1620, commenced dropping load to 70% to allow cleaning of main feedwater pump strainers.

Power reduced to 55%

to keep plant stabilized while cleaning strainers.

At 2200, commenced increasing load to 95% at 5% per hour.

Load increase in progress.

Load stabilized at 95% by 1600 and stayed there for the remainder of the day.

Load was stabilized at 95% power until 2010 when load reduction was commenced at 5% per hour.

Load reduction in progress at 5% per hour.

Load stabilized at 70% by 0200 to allow cleaning of condensate pump strainers.

Load increase commenced at 1245 at 3% per hour.

Load at 100% by 2330.

Load stabilized at 100%.

Load reduction commenced at 2200 to allow cleaning of condensate pump strainers.

1/23 Load decrease in progress.

Stabilized load at 70% at 0100.

Condensate strainers cleaned and increasing load by 0345 at 3% per hour.

Unit trip from 96% at 1029.

lH 460 volt group transformer dropped out of service which resulted in the tripping of a steam generator feedwater pump and a reactor trip on low steam generator water level.

Unit dow~ for the remainder of the day.

1/24 Reactor critical and load increase commenced at 1130.

Load being increased over the remainder of the day.

1/25 Load increase in progress to 100%.

Load stabilized at 100% by 1900.

1/26 1/27 Load stabilized at 100% power for the day.

Load stabilized at 100% until 2030 when a load decrease was commenced to 70% by 2300 to allow cleaning of condensate pump strainers.

1/28 Load increase commenced at 0115 from 70%.

Load stabilized at 100%

by 1030 for the remainder of the day.

1/29 Load stabilized at 100% until 2100 when load was decreased to 95%.

1/30 1/31 Page 17 of 18 Load reduced to maintain adequate NPSH to steam generator feedwater pumps which was dropping because of increasing differential pressure across the condensate polishing system.

Load stabilized at 95% while back-flushing operations continue with the condensate polishing system to reduce the differential pressure across the polisher vessels.

Load increased and stabilized at 100% by 1020 for the remainder of the day.

Load stabilized at 100% for the day.

~REFUELING INFORMATION January 1980 50-272 DOCKET NO.:

~------~

UNIT: Salem # 1 DATE: February 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

l.

Refueling information has changed from last month:

YES X

NO ---

2.

Scheduled date of next refueling:

September 20, 1980

3.

Scheduled date for restart following refueling:

November 16, 1980

4.

A.

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO-DATE January 1980 B.

Has the reload fuel design been reviewed by the Station Operating Review Co:mmi ttee?

YES NO x ---

If no, when is it scheduled?

August 1980

5.

Scheduled date(s) for submitting proposed licensing action:

August 1980 (If required)

6.

Important licensing considerations associated with refueling:

NONE

7.

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Fuel Storage 40

8.

Present licensed spent fuel sto~age capacity:

264 Future spent fuel storage capacity:

1,170

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

9.

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

September 1982 Page-18 of 18 8-l-7.R4

PS~G Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Nuclear Generating Station February 11, 1980 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of January 1980 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, H. J. Midura Manager -

Salem Generating Station LKM:vd cc:

Mr. Boyce H. Grier Director of U.S. NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 mo:i*m~y;.-. -~

tns:iqsures Ea" e 11 of 18

't..... ~E\\1~or 8--]i1>11*1<1 R4 95-2189 (4M) 3-78

AVERAGE DAILY UN IT POh1:R LE\\ 'EL ID NIH January 1980 DAY AVERAGE DAILY POWER LEVEL 1

2 3

4 5

6 7

~

9 10 11 12 13 14 15 16 Pg.

2 of 18 8.1-7.Rl (MWe-NET)

342 319 369 370 515 598 507 763 788 980 1,100 908 1,023 299 0

630 OOCKET KO. 50-272 UNIT Salem #1 DATE February 11, COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 x 507 DAY AVERAGE DAILY POWER LEVEL (MWE-NET) 17 924 18 943 19 1,047 20 833 21 1,069 22 1,092 23 379 24 96 25 856 26 1,069 27 1,084 28 1,021 29 1,048 30 1,114 31 1,114 1980

e OPERA.TIN:; CATA REPORT OPERATIN'.i STAroS

l. OnitNime:

Salem #1 Notes:

2.

~Period:

January 1980

3. Licensed 'l!lemal Pt:Mer (Kit):

3 3 3 8

6. M.3xillun Dependable Capacity 1Gross KtE):

112 4

~-....,,...,,...,,....,,.-----~

4.

Nairepl.ate Ratjng (Gross KrJe) :

113 5

~--~~~--~

5.

Design El.ecb:ical Ratjng (Net M'E) :

1 0 9 0

7.

Max:illllCll Dependable Capacity (Net KrJe) :

1 0 7 9 e

IXX:KET 00.: 50-272 DATE:

February 11, 1980 ClM'I.El'IDBY: L. K. Miller TEI.EPB::NE: 365-7000 X507

8. If Changes Occur in Capacity Ratings (Itms N1Jl!i:er 3 Thrcu;h 7l s~ Last ReFort, Give Reason:

NONE

9.

Power Level To Which ~cted, If Aey (Net Kiel:

NONE

10.

Reasons For Restrictions, If Aey:

NONE This Month Year to Date Cumul.ati ve 744 744 22,705 ll. Bc:rurs In ~g Period

12.. NullCer Of Hours Reactor Was Critical 696.4 696.4 10,784.4

13. Reactcr Reserve ShutcXlwn :burs 0

0 22.7

14.

Hours Generator On-Line 681.7 681. 7 10,212.8 lS. Onit ~

Shutdown Bc:rurs 0

0 0

16. Gross 'nlema.l Energy Generated(z.Hr) 1,789,716 1,789,716 29,326,013

17.

Gross Electrical Energy Generated (MWH) 586,080 586,080 9,753,580

18. Net Electrical Energy Generated (l+IH) 556,282 556,282 9,185,872

19. Onit Service Factor

91. 6

91. 6 45.0

20.

Unit Availability Factor

91. 6

91. 6 45.0

21. Onit Capacity Factor (Using MOC Net) 69.3 69.3 37.5

22. Unit Capacity Factor (Using DER Net) 68.6 68.6 37.1

23. Onit Forced Outage Rate 8.4 8.4 43.4

24.

Shutdcwns Scbeduled over Next 6 Mc:nths (Type, Date, and Duration of Each):

NONE

25. If Shut Down At F.nd of Report Periodr Estimated Date of Startup: _____

N_/_A _________.,_ __

26. Onits In Test Status (Prior tc Cattrercial ~tion) :

B-l-7.R2 Pg.

3 of 18

rnITIAL CRITiou.I'IY

rnITIAL EW:TRICI'IY al+lEX:IAI. OPERA'.l'IOO Forecast 9 /. 3.Q.L1.§ 11/1/76 12/20/76 Achieved 12/11/76 12/25/76 6/20/77

m.80-001 80-002 80-003 80-004 80-005 80-009 80-015 80-017 80-019 1

DATE 1/1/80 1/3/80 1/5/80 1/7/80 1/8/80 1/11/80 1/14/80 1/17/80 1/20/80 F:

Forced S: Scheduled Page 4 of 18 0-1-7.Rl TYPE!

F F

F 2

UNIT Sllll'IlXJ'INS 1\\ND PCMER REtix:rIONS REPORI' f\\Ulfill January 1980 MET1DD OF OOR1\\TICN

~

SlllJITIOO (llXJRS),

~

REAC'IDR 0

D 5

0 D

5 0

D 5

0 D

5 0

D 5

0 A

5 37.1 A

3 0

A 5

0 A

5 Reason:

A-Ek)uiµrent Failure(Explain)

&-Maintenance or Test C-Refueling O-Regulatory Restriction LICENSE EVEN!'

REPORI' I E--Operator Training & License Examination F-1\\dministrative G-{\\Jerational Error(Explain)

H-other (Explain)

SYSTEM CD1PrnENl' cmE" caJES SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz RH HT EX CH RB zzzzzz RH HTEXCH RH HTEXCH 3

~thcxl:

1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO.:

50-272 UNIT 1N1\\ME:

Salem Ill DATE:

February 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 CAUSE Mil OJRRECI'IVE 1\\Cl'ION 'ID PREVENI' REL'lJRREN:E NRC Tech. Specs./Reg. Guides NRC Tech. Specs. /Reg. Guides NRC Tech. Specs./Reg. Guides NRC Tech. Specs. /Reg. Guides NRC Tech. Specs./Reg. Guides Clean Condensate Pumps Suction Strainers Nuclear Instrumentation (Spurious noise spide on Power Range Channel N-43 while N-44 was in test).

Clean Condensate Pumps Suction Strainers Clean Condensate Pumps Suction Strainers 4

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (I.ER) File (NUREX}-0161) 5 Exhibit 1-Sane Source X507.

m.80-022 80-024 80-026 DATE 1/23/80 1/23/80 1/27/80 Page 5 of 18 8-1-7.Rl TYPEl F

F F

IXJRl\\TIOO

~2 (IUJR<l) 0 A

25.2 A

0 A

UNIT SllU'IU1'iNS MID l'04ER REnX:l'IOOS REroRT MJm1I January 1980 MlmlJD OF SllUITI?r.

LICENSE SYS'I'EM CXMPrnFm' IXMN EVENl' rooE"

<XJDES REllC'IUR REPORT I 5

RH HTEXCH 3

RH TRANSF 5

RH HTEXCH DOCKET NO. 1_5_0_-_2_7_2 __ ~

UNIT*NAMEI Salem #1 DATE*

February 11, 1980

~--------'~

COMPLETED BY:_L_._K_._M_i_l_l_e_r __ _

TELEPHONE: _6_0_9_-_3_6_5_-_7_o_oo __ x_s_o7 CAUSE Am CORR&:l'IVE ACTIOO 'IU PIU!.VENI' RIDJRREN.-:E Clean Condensate Pumps Suction Strainers Loss of Auxiliary Clean Condensate Strainers Transformer Pumps Suction

1 i

MAJOR PLANT MODIFICATIO~

REPORT Mt>NTH January 19~

DCR NO.

lED-0191 lED-0343 lEC-0438 lEC-0465 lEC-0561 lEC-0568 lEC-0623 lEC-0678 lEC-0683 lEC-0699 lMD-0051 lPD-0037 lSC-0018 lSC-0025 lSC-0046 lSC-0064 lSC-0112 PRINCIPLE SYSTEM Sampling Cathodic Protection Circulating Water Control Air Main Turbine Lube Oil Fire Protl!ction MSIV Containment Ventilation 4KV Vital Busses Containment Sump Reactor Head Aux. Temperature Indication Communications Fuel Handling Fire Protection Overhead Annunciator Control Room

DESIGN CHANGE REQUEST 8-1-7.Rl DOCKET NO.:

50-272 UNIT NA Salem Ill DATE:

February 11, 1980 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 SUBJECT Install Feedwater o2 Analyzer Install Ground Beds at S.W. Structure Modify Controls for Manual Operation Remove and Replace Piping for Condenser Retubing Install Lube Oil Filter Install Additional Aux. Building Hose Reel Remove Overload Jumpers on Hydraulic Pump Modify 1VC5 & 6 to Improve Operation Change Relay Setting Install Vortex Baffles and Reset Level Switches Modify Themocouple Trays Replace Bristol Recorders with the

Doric Install S.P. Phone at Pressurizer Modify Fuel Transfer System in Accordance With Westinghouse WRAPS Package Replace HP Turbine Fire Detector Modify Alarm Windows D-37 and D-45 Install Improved Clock Page 6 of 18

50-272 MAJOR PLANT MODIFICATI~

REPORT MONTH January 198u DOCKET NO.:

UNIT Ne::

DATE:

Unit tfl February 11, 1980

DCR NO.

lED-0191 lED-0343 lEC-0438 lEC-0465 lEC-0561 lEC-0568 lEC-0623 lEC-0678 lEC-0683 lEC-0699 lMD-0051 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 10CFRSO. 59.

SAFETY EVALUATION This change is not safety related and does not affect safety related equipment.

X507 This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unreviewed safety question per 10CFR 50.59.

This system is not safety related.

The change increases the fle~ibility of operat.ion without impairing reliability.

The type of materials employed in this change are identical to those used in the current design.

This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Technical Specifications are not affected.

This design change will not require a change to the Tech. Specs. or FSAR.

The additional filter equipment nor the surrounding equipment is safety related.

This modification will improve the main turbine lube oil cleanliness and increase reliability.

The installation of the hose station required by this DCR has been previously reviewed and it has been found that it does not present an unresolved safety question.

No additional fire hazard is introduced by the addition of this hose station.

It improves the plant safety features against fire.

The modification does not change the functional operation of the system nor degrade its performance.

The reworked valves will not adversely affect existing safety equipment or invalidate existing safety analysis.

This design change will assure that the valve closes when required to.

This change does not alter the functional design of the system.

It reflects preferred method of applying protective relays.

The existing design was necessary only because seismic data on pref erred design was not previously available.

No modifications affecting fire systems are made.

Implementation of this DCR will insure a safer shutdown of the NSSS equip-ment following an accident involving a breach in the primary coolant system by providing anti-vortex baffles in the reactor building sump pit on the suction side of the residual heat removal pumps.

Modifying the two cable trays does not involve any safety questions.

DES!GN CHANGE REQUEST Page 7 of 18

MAJOR PLANT MODIFICATI~

REPORT MONTH January 1980 DOCKET~.:

UNIT N DATE:

50-272 Salem tl1 February 11, 1980

DCR NO.

lPD-0037 lSC-0018 lSC-0025 lSC-0046 lSC-0064 lSC-0112 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 10CFRSO. 59.

SAFETY EVALUATION The system and ins.truments involved in this change are not safety related but the instruments are mounted in a Class I cabinet (lRPl).

Class I cabinet requirements have been considered for lRPl and have not been altered by this change.

This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unresolv~d safety question per 10CFR 50.59.

This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Tech. Specs.

are not affected.

This is not a safety related system and has no effect upon the safe shut-down capability of the plant.

This change is not functionally safety related and supports a design analysis revising the alarms so that the alarm windows remain "black" unless both the reactor power is above 50% and the quadrant power tilt ration exceeds 1.02. It is classified as safety related because the work performed will be in a safety related cabinet; This design change is not safety related and does not affect any safety related systems or the safe shutdown of the unit.

Page 8 of 18

l

DFSTGN CHA..i.'J'GE REOUESTU

Si1LEM GENERrYrii-lG STrYrIOi-l MONTHLY REPORT OF Si1FErr* RELr'1TED REF'rHRS O*jO!

J

!JORI\\

[1(.JTE PROBLEM DESCRIPTION DilTE DESCRIPTION OF REPAIR r.*"

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V_r'.\\LVE ll S.Jl *l3 Ht"iS F'F-*ic-1\\-. I_N_G __ L_E_F_il\\-. --------v--4 ___ l_l _7_9 _________ R_E_P._ti_C_l\\_E_D _______________ J:*

') ::L_:0""1""2"":"":'--~0_,.3_..2....

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~

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ASSEMBLED

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1 ll

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---*-----------~~~~~L~**E--D---------- -- *-- --

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"'5_29_J_cz__ ______ DI5(155Ei:ifil..ED l~:J 371---Ll.................___,,=-......,.<-<-'-----------'

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\\~J;,.. -~lvv~-----~/99 ____ -*------~R~EE

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Mf1CHii~E*r.;*-i:tisc & SE1H

- --ij J

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- - -*--*---------*-----~----

- - MAINTENANCE DEPARTMENT WORK ***

)

Page 9 of 18

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

SALEH GENERATING STATION MONTHLY REPORT OF SAFETY RELATED REPAIRS 0002 p

WORK MTE PROBLEM l'il::SCfUF'*TIOi-J DAlt

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__.5 ___ CDiHAINHEN.LEr'lbL.COI---------**----

ROUGHING FILTERS DIRTY

___ L5. AUX I LI 11R:f FEEDWflTER__ ____________..

PUMP START LIGHT DOES NOT LIGHT 08.l7 79 12 19 79

.l2 19 79 11 22 79 01.17.80 INSTALLED NEW GASKETS

1

.. - *-----:::*-:;;~:DF-0R-REF*-r1_rn_* -------* ---*- --l!:t RETURNED TO SERVICE

~

-*----::j REPLACED INTERNALS REPt-)CKED REPLACED DIAPHRAGM REPLACED f!LTERS_

REPAIRED_LIHIT SWITCHES ON VALVES 1H5132 AND.LHS52

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'"I SALEH GENERATING STATION HONTHLY REPORT OF SAFETY RELATED REPAIRS

(;003 WORK

[IATE PROBLEM DESCRIPTION Dr:ffE DESCRIPTION OF REPAIR

1-I.,

ORDER WRITTEN COHPLEIED_. ____...... -*

1

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r. _ __9.19.39-9 11.,5 79 -.......... --"""""--'<-<---------VAUJ.E.. H.i1Sl.68.....HA5-:E'.1\\CKllHLLEf'.\\K ____ -* ____..12_.06. 79.

PEP./~CKE~D _________ _

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nDU---------------*-------- -*---***.... *--................. *-**--*- *****----

to 919464 11 27 79 VALVE 12SJ40 HAS PACKING LEAK

~1 919539 12 "1

01 79 11 BORIC ACID TRANSFER PUMP SEAL LEAKING Ill-*---------------------

1g 919590 12 21 79 I

11 STEAM GENERATOR SNUBBERS

~'--

t:'*

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----* _ -~

2

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. :!l 17 79 INSTALLED NEW CUNOSEAL

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919627 11 16 79

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) I" 1;: 1 __ 919.625 11 16 79 I.

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VALVE llRC23 HAS PACKING LEAK 11 20 79 REPACKED VALVE 11RC17 HAS PACKING LEAK J.l 21 79 REPACKED

~----........_.~_,_, ________ _.,,V.ALVL.1...LRr.2iLHA.S.......£BCK.NcLLEAK..__. ________ U... 21-79 ____ ****--- ____.REF'.ACK~E~D _________ _

VALVE 11RC25 HAS PACKING LEAK 11 21 79 REPfiCKED VALVE 13RC17 HAS PACKING LEAK 11 22 79 VALVE 14HS18 HAS PACKING LEAK 11 17 79 REPr'.iCKED

. VALVE.....J.P5..l.3.-HAS.-EACKI.NG-LE(\\I\\. ______________ -*---- **-**-*-***.

.. _____..REP{tCKED _____________...

VALVE 14MS27 HAS PACKING LEAK 11 18 79 REPACKED VALVE 12MS10 HAS PACKING LEAK 11 18 79 REPfiCKED

.....__......__.._..,__.'-'----------V.ALVE.....J.2M51.B.JiA.S_E'.ACK.1N.ILLEfiK... ______ -*---...Ll. 17.... 79

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Page 11 of 18 I

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.I ORDER WRITTEN COMPLETED

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REVERSED.. INNER..Ar.w_o_UIER_ [IQOR INSPECT INNER DOOR GASKET SEALS

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~~---99-11-99-77-65-94--1-1-30_7_9 _________

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ro 12 05 79 VALVE 13RC25 HAS PACKING LEAK 12 05 79 REPACKED 1.,i I

1*-1

~r---7J.U.._7..._0 __ 1....,...._.o... s.._.7_.9'--_______

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CAGE AND SEAT OF VALVE

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-------*---**------------I-~~-r~LL_E_D_N_E_w_GA_s_K_'E_T_s_A_N_D_R_E_P_ACK~~- --

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9-.:1..9-774 12 05 79 I"

i*

~_._~.._.

_ _. _________ _.16_SERY.ICEJJflIE1Lf'UME_' ------

. ______ 12_2L.79. ________________ REBU.ILLF'.U.ME..._LOWER....1~55.EHBLY.____

I I

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9 INVESTIGATE HIGH VIBRATION REBUILT BY A&A COMPANY I

"1---~~~'----""'-'"""--'-----~------"'ALl'E-1.111.SLl:IA.S~LEAK__ ________.l.L..08..7.9 ___________ REPACKEI*-----------

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12 07 79 REPACKED JJ J-1 919785 12 06 79 VALVE l3MS168 HAS PACl\\ING LEAK 12 07 79 REPf-1CKED

) ~'--~~

9'19..Z.ll6 __

1~?~0~6~7~9--------~V.AUlE.-1.3MM.5....H~AK__ ______ _l2._08..J9 ___________ REF'.ACJ\\Erl~---------

J ~

919788 12 06 79 VALVE 14HS199 HAS PACKING LEAK 12 07 79

~r 929769 12 17 79 VALVE.LCV238 HAS BONNET LEAK------------------01--*02 00 ____ ---

)... I lt-* ---------

l q

929862 12 22 79 VALVE 11SW23 NO OPEN INDICA-

~ :1 TION IN CONTROL ROOM 12 O*I 79 REPACI\\ ED INSTALLED NEW DIAPHRAGM FIXED BUSHING REPLACED RELAY 33X-3

_I I.

I*,

I::

, l: ;t-1 929877 12 23 79 16 SERVICE WATER STRAINER BROKEN SHE(~R PIN 12 2*1 79 REPLACED SHEAR KEY AND BARREL SEAL PLATE 1**!

B 4,.----

*- !**i

)

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929922 12 27 79 VALVE 11HS167 WON'T OPEN 12 27 79 ADJUSTED PACl\\ING

~-1~2~2~7~7~9 ________

.CONTA I NHEN.LSPRffLAI*Dl.TI.VE ______ _

TANI\\ HANWAY LEAKING

_ _l2_3L79.

. INSH1LLED_GASJ\\E.L ON___ftD[*lU.V..E_ --.... -*....

FILLPIF'E b~---------------------------

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Page 12 of 18

lJORK DATE

~

ORDER WRITTEN t

I l

Q2_CZ.9-35 12 29 79 8 __

2,2.9~1 12 ?8 22 7

8

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12 30 Z2 II ti 13 931971 01 03 80

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)

3' 914476 01 06 80 co

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ct 914491

2 01 07 80 MONTHL"r" REPORT OF SAFET'r" RELFHED REPrURS 0005 PROBLEM DESCRIF'TION DrHE DESCRIPTION OF REPAIR COMPLETED

- ----*-****---------------__c_

1::> FUELHANDLil'lG_BUILil.I.NG._

.l.2-7_9 __ - - _. _________ REF.*.LACED.JRQl\\EN BELTS EXHAUST Fr::'tN* HAS Bl:;:OKEN BELT LL RESl.DU1'.JL..HEALREM.OVA1

__________ OL02-.80 _______

. __ REPAIRE[LM.J.CRQ SWITCH QN ACTUATING DEVICE

.---------,~i

... -* I,'/

SUMP ALARMS ON OVERFLOW I 3_STEluLELQW _V.£N.LVALV£.... ___________ J.2......3QJ9. _____

1:.1

.. ____ RE~CEDJJDNNEI O~fil_\\lE__

I..

-~'i::'i

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NEAR TRF,NSHITTER FT532 HF)5 BONNET LEM\\

1A Sr-)FEGLJr:iR[I EMERGENCY CABINET 01 03 80 REPLACED BAD RELAY INSPECT ION BY VENDOR PENETR1HION I-25 & I-26 01 09 80 RECHr4RGED 11 RECHARGE Fl ND CHECK FOR LE1)KS FOUND NO LEF)KS

'-----1~i[

1,,,

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- - PERFORMANCE DEPF)RTMENT WORK ***

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l::i N-31 SOURCE RANGE SENSITIVE TO 12 13 79 i:-1 i:-rTr::*Tr"ALNDl..51:"

REBUILT CABLE PLUGS

,.i

.EF~LACEIL...JACK.__ON_.E'.HD CIRCUIT

r

_.......,LU.U....... ~----***1/

N31 DETECTOR EXCESSIVE NOISE 10 19 7'1 SIGNAL ISOLATOR IN N-43 OUT OF 01 01 80 f':t.11 T R.Rail.'~;J REPLACED N3l F)ND N35 DETECTORS 1:'.;

_REBU~lll£1XI£il Pl llGS AT DRAWERS_.,,:*:

REPLACED SIGNAL ISOLATOR

_11M2.Q3£L.SERUJL (]0455 WITH 00453

'"I 1:,'.,

R31B FAILED FUEL PROTECTION 01 06 80

EMrs.iDW 01

L3 STEAM GENERATOR FEEWWATER FLOW 07 80 REPLACED BOARD !PB!

1~1

::~~:::E:rM....

~-~~-I_E_.R_' _B_o_A_R_D ____ e_~:::

'"L!ANNEI II rlI.DRllliG.E.__EA I I FD I

RECt)LIBRAI_

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) ::1 914521 01 09 80 VALVE l45W232 STRAIGHTENED LI HIT SWITCH I~

l,'.r------------------....1.-JLuLLS.W.LT..CH....ARlLBENc.c.I_____

_ ____ VERIFIED OF~ERE.\\.llfThl _______.

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915296 11 12 79 N4l CABLES SHORTED 11 14 79 LOCATED SHORT AND CLEARED IT r

N3l ___ [tETECJOR ____ VERJl:_Y PROPER -* -***. _. __ -----*-* __ 1_2. O:'.L"Z'i' ________..

____ REPLACED __ C1)B_l,,...E_E'LJJ!LON ___________ J, DETECTOR VOLTAGE AN[I HETER ACCURACY HIGH VOLTAGE POWER SUPPLY

~

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915322 12 05 79

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915615 11 15 79 I:

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1 919394

!1 24 79 SALEM GENERATING STATION MONTHLY REPORT DF SAFETY RELATED REPAIRS PROBLEM DESCRIPTION D{lTE COMPLETED N-42 SOURCE RANGE OUT OF SPEC VALVE 12SW223 DOES NOT CONTROL FLOW TO 12 CONTAINMENT FAN

!l :30 79

.1..L 25 79

____________.. ___ COIL._UiU.T

'l 919591 12 20 79

'JI "I

929776 1., 18 79 Vil VALVE 13AF21DOES NOT REGULATE 12 22 79 AUDIO COUNT RATE SOUND 12 19 79 DIST.DRIED I 17 929806 12 14 79 12 REACTOR COOLANT PUMP 12 18 79 IR 1-------------------LOW_SEfiLif:AILOELELOW _____ _

INDICATOR/TRANSMITTER STICKS 20 0006 DESCRIPTION OF REPAIR REPLACED MODULE XA5904RB WITH HOD~LE FROM UNIT 2 BLEW DOWN TRANSMITTER FA31652-1 r'1ND F(135*102J.

REPLfiCED_ (1Hf'.UEIEILiiLEA35402L..

REPLACED SQUARE ROOT

_. *-- EiCT:R1'.!CTOR __ rn~;971_I_(4W_DR.t... F.'D:-:0958 _

DISASSEMBLED AND CLEANED (J

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Page 14 of 18.

1._

SALEM UNIT #1 OPERATING

SUMMARY

JANUARY 1980 1/1 At 40% power, steady state conditions for entire day.

1/2 At 0330, commenced inserting rods by dilution to 140 steps to swing 6I negative in preparation for a flux map.

Power remained at 40% for the whole day.

1/3 At 0500 on 1/3/80, waiting for 6I to stabilize for power coefficient test.

Between 0640 and 0740, turbine load being increased then decreased.

At 0750, commenced increasing power to 47% at 3% per hour.

The reactor remained at 47% for the remainder of the day.

1/4 1/5 thru 1/6 1/7 thru 1/8 1/9 thru 1/10 1/11 thru 1/12 Page 15 of 18 Power remained at 47% for the entire day.

Power being increased from 48% to 60% on 1/5/80 in preparation for next physics test.

Once physics test was complete, power was reduced to 50% by 2400 on 1/6/80 to clean feed pump strainers and to evaluate quadrant power tilt.

Power remained at 50% until authorization was given to go to 80%.

At 2200 on 1/7/80, power escalation began at approximately 3% per hour.

Power was held at 80% for physics testing.

At 2115 on 1/8/80, reactor power reduction began from 80% to 65% power to clean condensate pump strainers.

At 1200 on 1/9/80, power escalation began at 1.5% per hour to 95% which is the next physics testing plateau.

Power remained at 95% through 1/10 while physics testing was in progress.

Still performing physics testing.

At 0630 on 1/11/80, commenced power reduction at 3% per hour down to 70% to clean condensate pump strainers.

At 2100, with strainers cleaned, power escalation began at 3% per hour reactor thermal power.

Power remained at 95% for the remainder of this period.

1/13 At 95% power until 1400 when load reduction in order to perform governor valve closure of #12 stop valve was commenced.

Load reduction terminated at 93% power and remained there for the remainder of the day.

1/14 Power escalated from 93% to 95%.

At 0956 on 1/14/80, reactor tripped from 95% on a false high neutron flux rate trip signal.

Reactor remained subcritical until 1013 on 1/15/80 when reactor was taken critical.

Remained at zero power until reactor tripped at 1630 on steam generator low low level.

Reactor brought critical until it tripped again at 1900 on steam generator low low level.

Reactor brought critical and power escalation began.

At 2400 on 1/15/80, power was 18.2%.

1/16 Power escalation continued.

At 1234, experienced turbine load swing due to E.H. control system malfunction.

Turbine placed in manual.

At 2400, reactor power was at 89.5%.

1/17 Power reached 95% at 0400.

At 1620, commenced dropping load to 70% to allow cleaning of main feedwater pump strainers.

Power reduced to 55%

to keep plant stabilized while cleaning strainers.

At 2200, commenced increasing load to 95% at 5% per hour.

1/18 Load increase in progress.

Load stabilized at 95% by 1600 and stayed there for the remainder of the day.

1/19 Load was stabilized at 95% power until 2010 when load reduction was commenced at 5% per hour.

1/20 Load reduction in progress at 5% per hour.

Load stabilized at 70% by 0200 to allow cleaning of condensate ptnnp strainers.

Load increase commenced at 1245 at 3% per hour.

Load at 100% by 2330.

1/21 Load stabilized at 100%.

1/22 Load stabilized at 100%.

Load reduction commenced at 2200 to allow cleaning of condensate ptnnp strainers.

Page 16 of 18

1/23 Load decrease in progress.

Stabilized load at 70% at 0100.

Condensate strainers cleaned and increasing load by 0345 at 3% per hour.

Unit trip from 96% at 1029.

lH 460 volt group transformer dropped out of service which resulted in the tripping of a steam generator feedwater pump and a reactor trip on low steam generator water level.

Unit down for the remainder of the day.

1/24 Reactor critical and load increase commenced at 1130.

Load being increased over the remainder of the day.

1/25 Load increase in progress to 100%.

Load stabilized at 100% by 1900.

1/26 Load stabilized at 100% power for the day.

1/27 Load stabilized at 100% until 2030 when a load decrease was commenced to 70% by 2300 to allow cleaning of condensate pump strainers.

1/28 Load increase commenced at 0115 from 70%.

Load stabilized at 100%

by 1030 for the remainder of the day.

1/29 Load stabilized at 100% until 2100 when load was decreased to 95%.

Load reduced to maintain adequate NPSH to steam generator feedwater pumps which was dropping because of increasing differential pressure across the condensate polishing system.

Load stabilized at 95% while back-flushing operations continue with the condensate polishing system to reduce the differential pressure across the polisher vessels.

Load increased and stabilized at 100% by 1020 for the remainder of the day.

1/30 Load stabilized at 100% for the day.

1/31 Load stabilized at 100% for the day.

Page 17 of 18

e REFUELING INFORMATION e January 1980 50-272 DOCKET NO.:

~-------

UN IT: Salem #1 DATE: February 11, 198~

COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

l.

Refueling information has changed from last month:

YES X

NO

2.

Scheduled date of next refueling:

September 20, 1980

3.

Scheduled date for restart following refueling:

November 16, 1980

4.

A.

Will Technical Specification changes or other license amendments be required?

YES NO ---

NOT DETERMINED TO-DATE January 1980 B.

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO x ---

If no, when is it scheduled?

August 1980

5.

Scheduled date(s) for submitting proposed licensing action:

August 1980 (If required)

6.

Important licensing considerations associated with refueling:

NONE

7.

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Fuel 'Storage 40

8.

Present licensed spent fuel storage capacity:

264 Future spent fuel storage capacity:

1,170

9.

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

September 1982 Page 18 of 18 8-l-7.R4

C~ PS~G Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Nuclear Generating Station February 11, 1980 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of January 1980 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, H. J. Midura Manager -

Salem Generating Station LKM:vd cc:

Mr. Boyce H. Grier Director of U.S. NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Corrunission Washington, DC 20555 l!Hl!M!liH,...(-'.

Enclosures Pa'de '1 of 18 "1*

1u1~m*

g.-..];i;ii,,q: R4 95-2189 (4MJ 3-7E

~NTI-I January 1980 DAY AVERl\\GE DAILY POWER LEVEL 1

2 3

4 5

6 7

~

9 10 11 12 13 14 15 16 Pg.

2 of 18 8.1-7.Rl

(}1We-NET)

342 319 369 370 515 598 507 763 788 980 1,100 908 1,023 299 0

630 AVERAGE DAILY UNIT POh"ER. LEYEL OOCKET NO. 50-272 UNIT Salem #1 DATE February 11, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 x 507 DAY AVERAGE DAILY POh1:R LEVEL (MWE-NET) 17 924 18 943 19 1,047 20 833 21 1,069 22 1,092 23 379 24 96 25 856 26 1,069 27 1,084 28 1,021 29 1,048 30 1,114 31 1,114

e

~

CATA REE'ORl' CPERAT!N3 STATUS

l. lJnitNama:

Salem #1 Notes:

2.

~Period:

January 1980

3. Licensed 'll1eI:m!J. Power (K<i't): __

..,,.3...,,.3....,,3-=8,,_ ___ _

4.

Na!!Epl.ate Rating (Gross !fi!) :

113 5

=-.,,..,,.-=-------

5.

t:esign Electric:al Rating (Net M<ie):

10 9.0

6.

Maxil!Ull Dependable Capacity '(Gross K-1e):

1124

7.

Maximlm Dependable Capacity (Net K-1e) :

10 7 9 e

rx:x::KET ro.: 5 O - 2 7 2 CATE:

February 11, 1980 o::MPIEm:lBY: L. K. Miller

~=

365-7000 X507

8. If Changes OcoJr in Capacity Ratings (Ite!rs Nlllii:er 3 ~

7) Since Last Repjrt, Give Reason:

NONE

9.

Power Ievel 'lb Which Restricted, If Any (Net K-1el : _______

N_O_N_E ____________ __

10.

P.easals For Restrictions, If Any:

NONE

'!his M::lnth Year to Date Clmll.ati ve 744 744 22,705

u. Hours In ~g Period 696.4 696.4 10,784.4

12. ~

Of S::lurs 1:2actor was Cri tic::al

13.

Reactor Reserve Shutdown Hours 0

0 22.7

14.

Hours Generator On-Line 681.7 681. 7 10,212.8

15. lJnit Eeserve Shutdown Iblrs 0

0 0

16. Gross 'nleJ:mal Energy Generated(~)

1,789,716 1,789,716 29,326,013

17. Gross Electr.i.ca.l Energy Generated (?-WI) 586,080 586,080 9,753,580

18. Net Electrical Energy Generated(Mm) 556,282 556,282 9,185,872

19. lJnit Service Factor

91. 6

91. 6 45.0

20.

1Jni t Ava n ahi Ji ty Fact:cr

91. 6

91. 6 45.0

21. lJnit Capacity Factor (Using MOC Net) 69.3 69.3 37.5

22. Unit Capacity Factor (Using DER Net) 68.6 68.6 37.1

23. Unit Forced Outage Rate 8.4 8.4 43.4

24.

Shutdcwns Scheduled ever Next 6 M:nths (Type, Date, and Duration of F.ach) :

NONE

25. If Shut Down At End of Report Period! Estimated Date of StarttJp: ______ N_/_A ___________ _

26. Units In Test Status (Prior tc Camercial cperation) :

S-l-7.R2 Pg.

3 of 18 INITIAL CRITIClU.I'IY INITIAL :E:UO'RICIT'i

~

OPERATION Forecast 9f-30/76 11/1/76 12/20/76 Achieved 12/11/76 12/25/76 6/20/77

ID.80-001 80-002 80-003 80-004 80-005 80-009 80-015 80-017 80-019 1

DATE 1/1/80 1/3/80 1/5/80 1/7/80 1/8/80 1/11/80 1/14/80 1/17/80 1/20/80 F: Forced s: Scheduled Page 4 of 18 8-1-7.Rl TYPJ!

F F

F 2

UNIT Sllt~S l\\ND PCMER ~IONS REPORT mwm January 1980 Mfil100 OF OORl\\TIOO

~

SlllTITim (ID.JRS)

IXMN REPCIDR 0

D 5

0 D

5 0

D 5

0 D

5 0

D 5

0 A

5 37.1 A

3 0

A 5

0 A

5 Reason:

A-Fl:)uiprent Failure(Explain)

B-Ma.intenance or Test C-Refueling LICENSE E.VENl' REPORT I

[)-Regulatory Restriction E--Q?erator Training & IJ.amse Examination F-.Administrative G-q>erational Error (Explain)

H--Other (Explain)

SYSTEM CDtPrnENl' CX>DE4 CCXJE5 SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz RH HT EX CH RB zzzzzz RH HTEXCH RH HTEXCH 3

M'.?thod:

1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO.:

50-272

~~~~~~~~~

UNITlNAME:

Salem #1 DATE:

February 11, 1980 COMPLETED BY: L. K. Miller

~--~....,.-,-~--~~.,---

TELEP II ONE: 609-365-7000 X507.

Cl\\USE 1\\ND OJRROCTIVE ACI'ION 'ID PREVml'~

NRC Tech. Specs. /Reg. Guides NRC Tech. Specs./Reg. Guides NRC Tech. Specs./Reg. Guides NRC Tech. Specs. /Reg. Guides NRC Tech. Specs./Reg. Guides Clean Condensate Pumps Suction Strainers Nuclear Instrumentation (Spurious noise spide on Power Range Channel N-43 while N-44 was in test).

Clean Condensate Pumps Suction Strainers Clean Condensate Pumps Suction Strainers 4

Exhibit G - Instructions for Preparation of Data Entry Sheets for IJ.censee Event Report (Lm) File (Nt.JRID-0161) 5 Exhibit 1-Sam:!

Source

m.80-022 80-024 80-026 01\\"ra 1/23/80 1/23/80 1/27/80 Page 5 of 18 8-1-7.Rl TYPE1 F

F F

DURl\\TIOO RE1\\SON2 (IDJRS) 0 A

25.2 A

0 A

UNIT SllU11XMNS 1\\NIJ PCMER rano'IOOS REroRT KJf>1I'H January 1980 HETIOO OF SlllJITltr.

LICENSE SYSTI:M cntPCNENr IXMN EVENI' rnoE4 aJOE5 l1FJICTOR REPORT I 5

HH HTEXCH 3

HH TRAN SF 5

HH HTEXCH 50-272 DOCKET NO.:~~~~~~~-

UNIT -NAME:

Salem Ill DATE:

February 11, 1980 COMPLETED BY:~L_.~K_.~M_i_l_l_e_r~~

TELEPHONF.:

609-365-7000 X507 CAUSE.ANJ a>RRFO'IVE ACl'ION 'IO PREVENI' RE:URREN'.:E Clean Condensate Pumps Suction Strainers Loss of Auxiliary Transformer Clean Condensate Pumps Suction Strainers

MAJOR PLANT MODIFICATIO~

REPORT M6NTH January 198P

DCR NO.

lED-0191 lED-0343 lEC-0438 lEC-0465 lEC-05.61 lEC-0568 lEC-0623 lEC-0678 lEC-0683 lEC-0699 lMD-0051 lPD-0037 lSC-0018 lSC-0025 lSC-0046 lSC-0064 lSC-0112 PRINCIPLE SYSTEM Sampling Cathodic Protection Circulating Water Control Air Main Turbine Lube Oil Fire Protection MSIV Containment Ventilation 4KV Vital Busses Containment Sump Reactor Head Aux. Temperature Indication Communications Fuel Handling Fire Protection Overhead Annunciator Control Room

DESIGN CHANGE REQUEST 8-1-7.Rl DOCKET NO.:

50-272 UNIT N~ Salem 111 DATE:

February 11, 1980 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 SUBJECT Install Feedwater o2 Analyzer Install Ground Beds at S.W. Structure Modify Controls for Manual Operation Remove and Replace Piping for Condenser Retubing Install Lube Oil Filter Install Additional Aux. Building Hose Reel Remove Overload Jumpers on Hydraulic Pump Modify 1VC5 & 6 to Improve Operation Change Relay Setting Install Vortex Baffles and Reset Level Switches Modify Themocouple Trays Replace Bristol Recorders with the

Doric Install S.P. Phone at Pressurizer Modify Fuel Transfer System in Accordance With Westinghouse WRAPS Package Replace HP Turbine Fire Detector Modify Alarm Windows D-37 and D-45 Install Improved Clock Page 6 of 18

DOCKET NO.:

50-272 MAJOR PLANT MODIFICATI~

REPORT MONTH January 1980 UNIT N&:

DATE:

Unit t/1 February 11, 1980

DCR NO.

lED-0191 lED-0343 lEC-0438 lEC-0465 lEC-0561 lEC-0568 lEC-0623 lEC-0678 lEC-0683 lEC-0699 lMD-0051 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 10CFRSO. 59.

SAFETY EVALUATION This change is not safety related and does not affect safety related equipment.

X507 This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unreviewed safety question per 10CFR 50.59.

This system is not safety related.

The change increases the fle~ibility of operat.ion without impairing reliability.

The type of materials employed in this change are identical to those used in the current design.

This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Technical Specifications are not affected.

This design change will not require a change to the Tech. Specs. or FSAR.

The additional filter equipment nor the surrounding equipment is safety related.

This modification will improve the main turbine lube oil cleanliness and increase reliability.

The installation of the hose station required by this DCR has been previously reviewed and it has been found that it does not present an unresolved safety question.

No additional fire hazard is introduced by the addition of this hose station.

It improves the plant safety features against fire.

The modification does not change the functional operation of the system nor degrade its performance.

The reworked valves will not adversely affect existing safety equipment or invalidate existing safety analysis.

This design change will assure that the valve closes when required to.

This change does not alter the functional design of the system.

It reflects preferred method of applying protective relays.

The existing design was necessary only because seismic data on preferred design was not previously available.

No modifications affecting fire systems are made.

Implementation of this DCR will insure a safer shutdown of the NSSS equip-ment following an accident involving a breach in the primary coolant system by providing anti-vortex baffles in the reactor building sump pit on the suction side of the residual heat removal pumps.

Modifying the two cable trays does not involve any safety questions.

DES!GN CHANGE REQUEST Page 7 of 18

MAJOR PLANT MODIFICATI<ta REPORT MONTH January 1980 DOCKET,O.:

UNIT N iE:

DATE:

50-272 Salem #1 February 11, 1980

DCR NO.

lPD-0037 lSC-0018 lSC-0025 lSC-0046 lSC-0064 lSC-0112 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 10CFRS 0. 5 9.

SAFETY EVALUATION The system and instruments involved in this change are not safety related but the instruments are mounted in a Class I cabinet (lRPl).

Class I cabinet requirements have been considered for lRPl and have not been altered by this change.

This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unresolved safety question per 10CFR 50.59.

This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The bases of the Tech. Specs.

are not affected.

This is not a safety related system and has no effect upon the safe shut-down capability of the plant.

This change is not functionally safety related and supports a design analysis revising the alarms so that the alarm windows remain "black" unless both the reactor power is above 50% and the quadrant power tilt ration exceeds 1.02.

It is classified as safety related because the work performed will be in a safety related cabinet.

This design change is not safety related and does not affect any safety related systems or the safe shutdown of the unit.

l- _D_E_S!GN CHANGE REQUEST Page 8 of 18

SALEH GENERATING STATION HONTHLY REPORT OF SAFETY RELATED REPAIRS 0001 l

WORI\\

MTE PROBLEM DESCRIPTION DATE DESCRIPTION OF REPAIR

~

H---'OB.D~E~R~_nWuR.IiTiT*EuN _________________.;...._ ___

~-

____.XOHPLEIED ______ ----- _

1

!----------------------*------------------~--

5

- - MAINTENANCE DEPARTMENT WORK ***

901366 Page 9 of 18

-..... ---*-------------------------)*

0002 I

[IESCRIPTION OF REPAIR

* ~l

)

1 WORK DATE PROBLEH l'.it'.SC~!F"TI0i'1 DAlE"

~1----'lllJo.=--IOl.l.>.."-'-LJ.J."------------------------------.l.o!OHPLEIE.D_. ___ _

SALEH GENERATING STATION MONTHLY REPORT OF SAFETY RELATED REPAIRS I

I'.

903061 04 21 79 VALVE l4AF23 HAS PACKING LEAK 12 08 79 REPLr,CE[I -BO_N_N_E_T_S_E-fi_L ______ G _____ -I~

REPilCl\\E[I I'..

1-----------------------------------------------------------*-**-------*--- --

903829

-: :1

)

~j 02 26 79 16 SERVICE WATER PUMP INSPECT & REPFiIR 03.. ois" 79 ---

-------- ~~-~- ~~s~;~~~iii~ ~~~[l~R FOR -:ORK l:.l

--- -- --l::i 905924 07 03 79 n

VALUE lSW22~ BINDING 08 21 79 REPOSITIONED BELL CRAN!\\

REPc-'.1Cl\\ED i..I i:;I

'./

- 1

~---*-,l~*.-.::1*

1311*--9-13_7_3_9 __

1_0_2_7_7_9 _________

l_A DIESEL GEi"ERATDR EXHAUST---------------------*----*-- -- --- -------INSTALLED NEW GASKETS

~ u MANIFOLD LEA~S 914344

)

17 ll 15 79 VALVE llHS45 HAS PACKING LEAK REP~1Cl\\ED

_ 12 ___ 07..7_9 _____________ REF:FiCl\\Er,r__

REPLACED BONNET SEAL "1--~

.. :LU4

_._,5...____.l.._.1.__..1...

5'-"-7_,_9 ________

_,._,VALVE l 2r'.i.E23_1::f H._S_E:f1.CKl.i'ilLLElil\\ __ _

)

?0 1_,.

9J._4_34.6~~--------Vf\\L9E_J.2BU..2

__ Hr)_S_EAC.KIJ~G __ LEf'.1K ____________ 1_2 07.. 7_9 _____________ REPFiCKE_['-r ----------

) :

914349 11 VALVE l4MS130 HAS PACKING LEAi\\

REPACKED

-~

~I I

~

I

)

~---9-1_4_3_9_1 __ 1_2 ____________

l_l_C_H_I_L_L_E_D_W_A_T_E_R_P_U-HP_R_U-~-G-H-~------~T~i-i~-----

~EPLACED BEARINGS

~

\\

J---ll144._,.,1cL7_--"-0..,_l_,,_,.._,,,_,,_ _______

~U-Cfil_LLEILWJ'.lT.EfU:'.lliif:_OlLER_LEfiKING.. __________ Ol_O~l_SQ... _____. ______ REPU1CED_t!ECJ:ff1~J.. c{l_l.,,_SEr'.\\L _____________ 1::1, I

REPLACED OIL SEALS 1*

) 1:l ___ 9.l..4.45_6_~0~1~~--~--------* LCl:llLLEIL..W.AIE£LEU.MP_TIUf'.f::I.NG ____________ Ol 05_8.V ___________ REf'Lf°iCED.._illlE:RLilAf~)S~----

________ 1:1*

1311

_; 1~:! ____ 9_1_~~--7_4 __

0_1 ___________

~-~~-E

___ 1!~_w2_4_F_L_A_N_G_E_L_Efi_K ____ ~------- ----* -~~ -~-5-~~---

------~N~T-f~LLED NEW Vf1LVE BODY ----- ----

.. ::(

,* 1;:'1 915871 OB W1LVE lRH26 H(1S PfiCKING LEFiK 08 17 79 REPACKED 1::1

'I

l 1,- !')----9_: 1,_58Z_8 __

0_8

~~--------YALYE__.l_lJ3:1:f_1_Q_H_A.S_E'.J~C-~.l.NG __ l-E;_i11\\ __________ 08...L 7 __ z_9 _______.

REF:(1Cl\\_ED__________

1.-,

1

) :\\__

915880 _o_a_______

VALVE llRH:l8 HriS PACl\\ING LEf°1K 08 17 79 REPi1Cl\\ED e i-.1'-

) f,:1 916090 12 VALVE i4AF_2_l_LE-.. 1-)K-.S-THRU _________________ i219 "79-- -

. -- ----- ~~~t~~-~~IF~~ ~~~~~~E----* --- -----

i:L (I

. 1::1----9-16_0_9_2--12---------*

Vf.1LVE l-r-iF-2--l-LEr-:1K-.S-T-HRU ____________ ------ -1*2-*-19*-7*9--

-REPLr)cED INTERNALS i:".i, I

REF'r_' __ c_l\\Er __

.~-~1"'

REPL,.lCED DlflF'HRf,GH 1****1

).;,

917436 ll VALVE.L3SW264 LEril\\S THRU ll 22 79

,. i(.

!----9.1750_2_~11...._.......__....._.'---- _____

.....L.5.... CCJiHAINHENLFrtiLCDI-----------------

__ REF.'LfiCE[I F.lLTERS ________ ---- ------ --.i.. :1' j "'i ROUGHING FILTERS DIRT"!"

L:; l

~l _____ ~).75_6_~~~11~~~----* __________ 1_4_ CfJN_TAINHE_NT_f'"_riN _SOii _______________________. _ll 26 79 REPLr'.\\CED FILTERS I

ROUGHING FILTERS DIRTY

)

~.*,

I 910051

) if,[~=----* -

01

___ J.:3. AUXILifiR)' FEEDWfiTER_ ________________ _

PUMP START LIGHT DOES NfJT LIGHT 01.17 81i REF.'AIRED_LIHIT SWITCHES ON VALVES lHS.L32 AND.LHS52

.: I*.

'.I,,,

i I

I..

Page 10 of 18

""\\

)

SALEH GENERATING STATION MONTHLY REPORT OF SAFETY RELATED REPAIRS 0003 WORI\\

[IATE

'Lj CllUIER WRITTEN PROBLEM DESCRIPTION

[lrHE COHPLEJED _____ _

[IESCRIPTION OF REPAIR

1

,r*---919390 11 25 79 VALVE 12HS168 HAS PACKING LEAK 12 05 79 REPACl\\E-[1---*-------:-(-- -- - ---

G _ __919.39.9 11

>5 79

~--~~~--------VALV.L 1"1ii5L68_.HA5-:F-'1\\CKI.Nii_LEf?tK __________ __l.2 __ 06_ 79.

PEPACl\\E~fl _________ _

B 919450 11 26 79 VALVE 1PS2 HAS BROKEN REACH 11 28 79 REPAIRE[I REACH ROD

__________________,.o....__ _____________________ -**----* -****

to 919464 11 27 DI 919539 12 01 "1

79 79 VALVE 12SJ40 HAS PACKING LEAK

11. BORIC ACID TRANSFER PUMP SEAL LEAKING 11 28 79 REPACKED 12 04 79 REPLACE[! MECHANICAL SEAL

~1

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

I 919590 12 21 79 11 STEAM GENERATOR SNUBBERS 12 21 79 DRAINE[! OIL

1_

f~I 919592 12 21 79 SIGHTGLASS LEAKING TIGHTENED SIGHT GLASS

- ----- _ --~

2

~~-~-;- ---*-------::~:::*:1Lfilill__llGHIENED_EACKIN.

VITAL HEAT TRACING in, __________________

_._,E1'.l~E:L0.6.0.2BJ111LJJD.RK1NG__ __ _

112 J "

919593 12 21 79 REACTOR HEAD INSTRUMENT

~~--P.DRJ_C.UND5.Bi~I -------

REPLACE GASl\\ETS 919616 VALVE 11RC23 HAS PACKING LEAK VALVE l1RCl7 HAS PACKING LEAi\\

VALVE 14HSl8 HAS PACKING LEAK 919681 VALVE 14AF23 HAS PACKING LEAK

.:!l 17 79 INSTALLED NEW CUNOSEAL

___________________ GASKEIS. ______________.

REF'.ACKED ___ _

11 20 79 REPACl\\ED 11 21 79 REPACKED 11 18 79 REPACl\\ED 1l 18 79 REPr\\Cl\\ED

---*- __ REPf'\\Cl\\ED ___________ --.. -* - --

ll 17 79 l.I. 2.I. 79 REPF°1Cl'ED I.

! i 1.~.

I

--- *---1' Page 11 of 18 I

1*

J*

I

919703 11 18 79 919753 11 30 79 15

4:>1-1~.t:--n*--l.'l:'"Nl:.t\\H I ll'll3 b I 1-11 ll.IN ***-- ** * -

MONTHLY REPORT OF SAFETY RELATED REPAIRS PROBLEM DESCRIPTION VALVE 13SJ138 HAS PACKING LEAK AIRLOCICELEVATION _100 _____ ------------

INSPECT INNER DOOR GASKET DfHE COMPLETED

.. ----------lL.21.79--

11 21 79 11 21 79

- 11 20_ 79 -

_ll __ 24_ 79 __ ----

12 05 79 0004 DESCRIPTION OF REPAIR

..... REPACJ\\ED -----

REPACKED -------------*** - --

REPACKED REVERSED __ I NNER..AND_JJ_UIER_ DOOR SE{1LS

_. ___ REPACKE[1 REPACKED

!r r,

i",;

I*

I j I

\\'

-' i 161--- ----------~--------- ------------*------*-----*-----*---

-*-*-*-1' 919754 11 30 79 VALVE 13RC28 HAS PACKING LEAK 12 05 79 REPACKED 1

~ tt CLEANED BORON OFF VALVE I I r 1 IC e***

-11 a

919769 12 05 79 VALVE 13RC25 HAS PACKING LEAK 12 05 79 REPACKED

I 1 '° I.,.

I 1-1

)

~.~,*.cr----='-1.22.....

Z.>L0 __ 1

...... :i.._.o_...5...._.7_.9'---_______ JJ.AU.lE---1.2AE"1 l Eflh:.5-IHRU___ ---------.... 12_12 79 _____ --**-* ---* _REF.'LAC.ErLS.I-E~M_____

---*- - -'1*

.i.:

~

CAGE AND SEAT OF VALVE INSTALLED NEW GASKETS AND REPACKED

~------------- -----*

a 919772 12 05 79 VALVE 1CV79 HAS PACKING LEAK 12 05 79 REPACKED

)

111

\\. I.

n

£1..9-..... 7.....

7~4 __

1~2~* _,0~5..__.7_.9 ________ _...16 __ SERY.ICE__W(lIER_f'UME_' -----

______ 12_21-2_9 ________________ REBU.ILLf*_Ut!e_.__t._DWER_J)55EHI!Li'._ ___..

) ~

INVESTIGATE HIGH VIBRATION REBUILT BY A&A COMPANY I

311--_

_.9c..o1_,_9..._Z~B_...3 _ _....1?.._,0.,_.6..__.7_.9'-----------"VALilE-1.111.~HaS~LEAK__ ________ _l_L08 -79 ___________ REF.'ACl\\ED___________

-1..:

)

32 919784 12 06 79 VALVE 11MS168 HAS PACKING LEAK 12 07 79 REPACKED 33 919785 12 06 79 VALVE 13HS168 HAS PACKING LEAK 12 07 79 REPf-1CKED

)

~, __ __,_..._

919.2a..._6 __

1.._.?......_.0u.6._,_7.J.9 ________

..:.V.AUlE..._13MS~!LHas.......E:ACKIAl\\_ ______ 2__08-79 _________ REf'.ACJ\\EI.1_ ----------

J ~1 12 06 79

- I 919788 VALVE 14MS199 HAS PACKING LEAK

=r 929769 12 17 79 VALVE 1CV238 HAS BONNET LEAK J,.. I l"f------------------

I Q

929862 12 22 79 VALVE 11SW23 NO OPEN INDICA-

~ ~

TION IN CONTROL ROOM

)::,1 929877

B 12 23 79 16 SERVICE WATER STRAINER BROKEN SHEf.lR PIN 12 07 79 01 02 BO 12 0*1 79 REPACKED INSTALLED NEW DIAPHRAGM FIXED BUSHING REPLACED RELAY 33X-3

(:

1... ;

r, I

------*-*-M---*---*---------* ---- --

-**.. ' I REPLf'1CED SHEAR KEY AND

r Bf°lRREL SEAL PLATE

.L2 24 79

!--j

..J 511 929922 12 27 79 VALVE 11HS167 WON'T OPEN 12 27 79 AD~USTED PACKING 12 27 79 CONTAINMEN.LSPR((LADDI.JLVE_______

_ _______.12.... 3L79

... _ INSTf.1LLEILGASl\\E_T __ Oif_A[1[1;u_1_V_E ________...

) 1'.~

TANK HANWAY LEAKING b~---------------------------

) t'.l __ _

Page 12 of 18 FILLPIF'E

,1

' I I

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

o_~-----1 1,----- ----*-

MONTHLY REPORT OF SAFETY RELATED REPAIRS

""I

"'I

'.)

)

WORK DATE ORDER WRITTEN PROBLEM DESCRIPTION Dr:ffE COHF'LETED DESCRIPTION OF REPAIR

~ f-"+-------------------------------------------------- --***-

Q2CZ2_3::.i 12 29 "70

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SALEM UNIT Ill v

OPERATING

SUMMARY

JANUARY 1980 1/1 At 40% power, steady state conditions for entire day.

1/2 At 0330, commenced inserting rods by dilution to 140 steps to swing 61 negative in preparation for a flux map.

Power remained at 40% for the whole day.

1/3 At 0500 on 1/3/80, waiting for 61 to stabilize for power coefficient test.

Between 0640 and 0740, turbine load being increased then decreased.

At 0750, commenced increasing power to 47% at 3% per hour.

The reactor remained at 47% for the remainder of the day.

1/4 1/5 thru 1/6 1/7 thru 1/8 Power remained at 47% for the entire day.

Power being increased from 48% to 60% on 1/5/80 in preparation for next physics test.

Once physics test was complete, power was reduced to 50% by 2400 on 1/6/80 to clean feed pump strainers and to evaluate quadrant power tilt.

Power remained at 50% until authorization was given to go to 80%.

At 2200 on 1/7/80, power escalation began at approximately 3% per hour.

Power was held at 80% for physics testing.

At 2115 on 1/8/80, reactor power reduction began from 80% to 65% power to clean condensate pump strainers.

1/9 At 1200 on 1/9/80, power escalation began at 1.5% per hour to 95% which thru is the next physics testing plateau.

Power remained at 95% through 1/10 1/10 while physics testing was in progress.

1/11 Still perforniing physics testing.

At 0630 on 1/11/80, commenced power thru 1/12 Page 15 of 18 reduction at 3% per hour down to 70% to clean condensate pump strainers.

At 2100, with strainers cleaned, power escalation began at 3% per hour reactor thermal power.

Power remained at 95% for the remainder of this period.

l L./13 1/14 At 95% power until 1400 when load reduction in order to perform governor valve closure of #12 stop valve was commenced.

Load reduction terminated at 93% power and remained there for the remainder of the day.

Power escalated from 93% to 95%.

At 0956 on 1/14/80, reactor tripped from 95% on a false high neutron flux rate trip signal.

Reactor remained subcritical until 1013 on 1/15/80 when reactor was taken critical.

Remained at zero power until reactor tripped at 1630 on steam generator low low level.

Reactor brought critical until it tripped again at 1900 on steam generator low low level.

Reactor brought critical and power escalation began.

At 2400 on 1/15/80, power was 18.2%.

1/16 Power escalation continued.

At 1234, experienced turbine load swing due to E.H. control system malfunction.

Turbine placed in manual.

At 2400, reactor power was at 89.5%.

1/17 Power reached 95% at 0400.

At 1620, commenced dropping load to 70% to allow cleaning of main feedwater pump strainers.

Power reduced to 55%

to keep plant stabilized while cleaning strainers.

At 2200, commenced increasing load to 95% at 5% per hour.

1/18

.Load increase in progress.

Load stabilized at 95% by 1600 and stayed there for the remainder of the day.

1/19 Load was stabilized at 95% power until 2010 when load reduction was commenced at 5% per hour.

1/20 1/21 Load r,eduction in progress at 5% per hour.

Load stabilized at 70% by 0200 t.o allow cleaning of condensate pump strainers.

Load increase commenced at 1245 at 3% per hour.

Load at 100% by 2330.

Load stabili~ed at 100%.

1/22 Load stabilized at 100%.

Load reduction commenced at 2200 to allow*

cleaning of condensate pump strainers.

Page 16 of 18

"JP/ 23 Load decrease in progress.

Stabilized load at 70% at 0100.

Condensate strainers cleaned and increasing load by 0345 at 3% per hour.

Unit trip from 96% at 1029.

lH 460 volt group transformer dropped out of service which resulted in the tripping of a steam generator feedwater pump and a reactor trip on low steam generator water level.

Unit down for the remainder of the day.

1/24 Reactor critical and load increase commenced at 1130.

Load being increased over the remainder of the day.

1/25 Load increase in progress to 100%.

Load stabilized at 100% by 1900.

1/26 1/27 Load stabilized at 100% power for the day.

Load stabilized at 100% until 2030 when a load decrease was commenced to 70% by 2300 to allow cleaning of condensate pump strainers.

1/28 Load increase commenced at 0115 from 70%.

Load stabilized at 100%

by 1030 for the remainder of the day.

1/29 Load stabilized at 100% until 2100 when load was decreased to 95%.

1/30 1/31 Page 17 of 18 Load reduced to maintain adequate NPSH to steam generator feedwater pumps which was dropping because of increasing differential pressure across the condensate polishing system.

Load stabilized at 95% while back-flushing operations continue with the condensate polishing system to reduce the differential pressure across the polisher vessels.

Load increased and stabilized at 100% by 1020 for the remainder of the day.

Load stabilized at 100% for the day.

REFUELING INFORMATION January 1980 50-272 DOCKET NO.: ~~~~~~~~

UNIT: Salem #1 DATE: February 11, 19 8,j COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

l.

Refueling information has changed from last month:

YES X

NO ---

2.

Scheduled date of next refueling:

September 20, 1980

3.

Scheduled date for restart following.refueling:

November 16, 1980

4.

A.

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO-DATE January 1980 B.

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO x ---

If no, when is it scheduled?

August 1980

5.

Scheduled date(s) for submitting proposed licensing action:

August 1980 (If required)

6.

Important licensing considerations associated with refueling:

NONE

7.

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Fuel Storage 40

8.

Present licensed spent fuel storage capacity:

264 Future spent fuel storage capacity:

1,170

9.

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

September 1982 Page 18 of 18 8-l-7.R4

ML18081B051

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