ML19030A326

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Submit Monthly Operating Report for the Month of July 1978 for Salem No. 1
ML19030A326
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/10/1978
From: Midura H
Public Service Electric & Gas Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML19030A326 (23)
v • d • e


Text

.REGUlPaTORY DOCKET FILE COPY Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038

~~'1 o:-

Salem Nuclear Generating Station Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 -**'..J..'

~~~

c:>

-~*.

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 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 Opera ting Surmnary Refueling Information Sincerely yours,

µ9~

H. J. Midura Manager - Salem Generating Station LKM: jcm 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 Co!ltrol rno:i~l!.1-.:.. Nuclear Regulatory Commission

~~ington, D.C. 20555 Enc.

  • nrn1s01' sEm'lrn Page 1 of 23 8-l-7.R4 95-2189 (4M) 3-78

J '

e AVERAGE DAILY UNIT POWER A OOCKET NO. 50-272 UNIT . Salem #1 DATE August 10, 1978 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 MONIH July, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWE-NET) 1 737 17 1068 2 123 18 286 3 557 19 0 4 623 ----

20 *O 5 963 21 226

~-,

\ . _,.: 6 . 1024- 22 975 1088 23 1067 7

8 946 24 1054 9 1040 25 834 10 996 26 913 11 865 27 1021 1037 990 12 28 13 1082 29 . 1050 14 962 30 1038 15 1047 31 1061 16 . 883

\ / .

...__,, Pg. 2.- of 23 8.1-7.Rl.

~ N:l.:. _ _50-272 _ _ _ _ _ _ __

~  : _..:.A,::,,u::.;;igus~t.......,l::.:0....--=1:.::.9..:..7..._8_

o:ME'LE'lEJ BY:._L~.,...;K..;.;*~Mi;;;;';;;;;;l.;;;;le.;.r~....,,,.,~

~~:_6_0_9_-_36_5_-_7_0_oo_xs_o_7_

. OnitNane: ___s_ai_em ........_#_1_____________

1 Notes:

2.  ?.ep%tinq Ped.od: _ _ J_Ul_,y....._,....1-..9._7....8.___ __,__ _ __
3. Licensed 'lllecal ~ (Molt) : 3338
4. Nai:nep.Lats Rat:inq (Gmss mai: ---11-3-5------
s. Desig;i ElectriCal Rat::inq met~): _1....0....9....o______
6. Maxlllun I"'epe!'ldable capac:iey (Gross ~): 1124
7. ~.axm.im- rep=nciable <:apad.t'f (Net ~l: 1079
a. u Changes Cccur in capacit-.l Ratiz:.gs (I!:etts Nuiri:er 3 'n1l:cuqh 7) S.i.nc::e Last Ps;ort~ Give P.eascn:

None 9.

10. Reascns :or Rsstrli::-..ions, u Mr;{:

Power tevel To w1'lich Rest:d.c:'"..ed, If Aey (Net me) : __N_o_n_e_-- - - - - - - - - - - - - - - - - - - -

None

....;;.;.;~;;._--------------------

'Ihis ~th ---- Year tc Oats . CmllatiVe -

744 5087 . 9528 ll. Hours In Rep::~...:i.nq .Pa--rlod

12. - Nml:er Of 5:11rs* Peactor was Critic:al 666 2601.5 5144.7
13. Bear:tcr Paserve Shu~ E::lurs 0 0 0
14. aours Generator on-LL~e 652.9 - 2420.2 4850 *.8
15. ....."e Shul:::cwn EQurs tl'nit PeSe.. 0 0 0
16. Gmss 'nlet::l2l Energy Gelerated (~"'H) 1,933,495.2 - 7 ,168,869.4 13,864,089.4
17. Gross Electrical Ecergy Ge:lerated U.'lM1) 642,8So 2,426,490 4,612,soo
18. Net Elect:d.cal Ene..-.ogy -Gece..~ted (l~li) 611E725 -. --i E292*~*s16* -- 4E15Q,734
19. tl'nit Service Factcr . 87.8 47.6 50.9
20. trnit Avai1ability Factor 87.8 47.6 50.9
21. lJni t_capaci't'i_ Fact:Qr_ (Usi;lq MD: Net) 76.2 41.8 42.3 ---- --- --
22. Unit Capacit</ Factor (Usinq DER Net) 75.4 41.3 41.9 23 *. Unit Forcsd Outage !'.a.ts 14 7 52.6 38.6
24. Shutdcwns Scheduled aver Next: 6 M:nths (Type, Oats, and Duration of Zach) :
23. I! Shut eo.m At E::d of P.e;Qrt Pe..""ii::d~ Est:imate:i Date of Sf:art'..:p: - - - - - - - - - - - - - - - -
26. - Units In Test Stat::JS (Prior to camercial C9era.tion) :

Forer...ast Adlieved 9/30/76 12/11/76 8-l-7.R2 11/1/76 12/25/76 12/20/76 6/30/77 Page 3.of 23

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  • , , I

! i UNIT smiTro-INs AND lU'JER REDljcrIONS DOCKET NO. : _ _ _ 5_0_-_2_1_2___

I

. ' j REPORI' IDNI'H July,, 1978 UNIT :NAME: _ _ s_al_em

__#_l____

DATE: August 10, 1978 COMPLETED D~: L.K. Miller TELEPHONE: 609-365-7000 X507

! *, ' :ME:nm

' OF I 1

OORATION . RFJ\5002 SHtJITIOO LICEmE SYSTEM CXMPCNENr CAUSE AND OORRECrlVE

00. DATE . TYPE (OOURS) . '

[(MN . EVEr'li' 000£4 OODES ACTION 'ID

(* RFllCTOR REPORT 1. PREVENI' REOJRRENCE

,. i I

I Cl~an 12 Heater Drain Pump Suction 78-59 7-1-78 F 0 B 4 - -- - HH Filter Strainers.

78-60 7-1-78 F 0 B 4 ... --- - HH Filter Clean* 12 Heater Drain and Condensate Purrp Suction Strainers.

/

78-61 7-1-78 F 0 A 4 - - - - Ha Filter Clean 12 Heater Drain Pump Suction1 Strainers.

78-62 7-1-78 F 0 A 4 - - - - :HH Filter Clean 12 Heater Drain Pump Suction Strainers.

78-63 7-1-78 F o* A 4 - - - - HH Filter Clean Feed Pump and Condensate Pump Suction Strainers.

1 2 3 4 5 F: Forced Reason: ~thod: Exhibit G - Instructions Exhibit 1-Sane l.:.Manual for Preparation of Data Source S: Scheduled A-:Equiprent Failure (Explain)

  • &-Maintenance or Test 2-:-Manual Scram. Entcy Sheets for Licensee C-Refueling J~Autanatic Scram. Event ~port(LER) File D-Regulatory Restriction 4j<>ther (Explain) (NUREI}-0161)

E--Operator Training & License Examination- , '

Page 4 of 23 F-1\dmi.nistrative ' ' ,

8-l-7.R2 G-q;ierational Error (Explain) I (I.Dad Redqct1on)

H--Other (Explain) '

I.

A~V1*:

( -(d

) \.. ~:

-:"-~

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UNIT SHtn1X>>IS 1\ND l'CMER REOOCTIONS DOCKE'r NO.: 50-272

' i ~~~~~~~~~

REPORr MJNm

  • July, !1978 UNIT*Nl\ME: Salem #1

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

DATE: August 101 1978 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 Mm'OOD OF 1 OORATIOO SIRJITIOO . LICENSE SYS'l'EM CXJ1PClllENl' CAUSE AND OJ~IVE NO. DATE TYPE (lkXJRS) ~ IXMN EVENr OJDE4 OJDE5 ACrION 'IO REl\C'IDR RE!?ORI' I PREVENI' REL'URRENCE I

78-64 7-1-78 F 15.26 A 2 ,.  ! H~ Turbin Manual Reator Trip-Due to Turbine E.H. Control Malfunction.

78-65 7-3-,78. F 0 A 4 - - - - HH Valvex *Repair 11 Steam Generator Feed Pump Recirc. Diaphragm.

i I'

78-66 7-3-78 F 0 A 4 - - - - HH ValveX: Repair 11 Steam Generator Feed PurrP Recirc. Diaphragm.

78-67 7-5-78 F 0 A 4 - - -- HH Filter Clean 12 Heater Drain Pump Suction Strainer*'.*

I I

78-68 7-5-78 F 0 A 4 - - r- - HH Filter Clean 12 Heater Drain Pump Suction I

,,I Strainer.

' I I

I l '

78-69 7-5-78 F 0 A 4 - -  !;..

j*

- HH Filter Clean 12 Heater Drain Pump Suction I

I i Strainer.

i I

78-70 7-7-78 F 0 A 4  :

- - HH Filter Clean 12 Heater Drain Punp Suction I, strainer.

I l

Page 5 of 23 a-1-?*G (_)'\

~:_/

'l.

trnIT SllUlOO'INS 1\ND IU'lER REll,X:l'lOOS I" J *' POC({ET NO. 1 ="""""_5_0~--2_7_2~--

Rro.'ORT MJrmf  ;*July, 1978 . UNIT 'NAMEI Salem #1 DATE: August 10, 1978 .

COMPLE'.l'ED BY: _ _L_._K_._Mi_'_l_le_r TELEPHONE: 609-365-7000 X507 METIDD OF '

OORATIOO SHlJITIOO LIC>>ISE SYSTEM CI:MPCMNl' CAUSE AND C.URIU'Cl'IVE NO. DATE TYPEl (R:XJRS) ' ~ DCl'lN EVEN!' CXJDE4 CXJDE5 ACfION 'ID RFJCroR REPORT I PREVENT REl'.:lJRRmCE I

78-71 7-7-78 F 0 A 4 -- r,;

I

- HH Filter Clean 12 Heater Drain Punp Suction Strainer.

78-72 7-8-78 F 0 A 4 - - TI - *i HH Filter Clean 12 Heater Drain Purrp Suction

' :1 "

Strainer.

(

1:

I .I 78-73 7-8-78 F 0 A 4 -- "r'

- HH Filter Clean 12 Heater Drain Punp Suction

' strainer.

I 78-74 7-8-78 F 0 A 4 - - 7. - HH Filter Cleari 11, 12, and 13 Condensate Purrp

Suction Strainers.

p 78-75 7-9-78 F 0 A 4 - - T' - HH Filter Clean 12 Heater Drain Punp Suction

' i Strainer. ..

,. I 1';

78-76 7-9-78 F 0 A 4 -- -- ;i 11 HH Filter Clean 12 Heater Drain Purrp Suction Strainer.

i *

i 7-9-78 F 0 A 4 ..,. - ' - HH Filter Clean 12 Heater Drain Punp Suction 78-77 "

f*'

Strainer.

i i

Page 6 of 23 ' '"

8-1-7.R!>.,

. *. 'U (f\

w l.

DOCKET NO. 1 50-272

! UNIT :NAME I --s,.-a-=1-em--...-#1~---

DATE: August 10, 1978"

' COMPLETED BY: . .

L K Miller

\

i  :

TELEPHONE: 609-365-7000 X507

ME:l'HJD OF OORATIOO SlltJl"l'IOO LICENSE i SYSTEM ClM'OOENl' CAUSE .!\ND OORRECI'IVE

' 00. DATE ~El (IDJRS) ~ DOON EVENr OODE4 OODES ACI'ION 'IQ RFJ\C'IDR REPORr I PREVENI' ROCURRENCE I

I' 78-78 1-10:..18 F 0 A 4 - -

I I-i1

- HH Filter Clean l~ Heater Drain Purrp Suction Strainer.

78-79 7-10-78 F 0 A 4 - - -' - HH Filter *Clean Steam Generator Feed Punp and

.. Condensate Punp Suction Strainers.

/

J 78-80 7-11-78 F 0 A 4 - - T - :tIB Filter Clean 12 Heater Drain Punp Suction

  • Strainer.

78-81 7-12-78 F 0 A 4 --- - I HH. Filter Clean 12 Heater Drain Punp Suction Strainer.

78-82 7-13-78 F 0 A 4 - - - - HH Filter Clean 12 Heater Drain Purrp and Condensate Punp Suction Strainers.

78-83 7-14-78 F 0 A 4 - - 1_ - HH Filter Clean 12 Heater Drain Purrp Suction Strainer.

78-84 7-15-78 F 0 A 4 --- - HH Filter Claen 12 Heater Drain Purrp Suction Strainer.

Page 7 of 23 ' '

8-1-7

  • BP ... "

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'** ... *- \.__)

r' i .,

UNIT SIR111Xl'INS llNo PrnER RIDX::TIONS DOCKET NO. : _ _ 5_0~--27_2~--

. i U

' Uly I REPORI'MJW'ff___....1_ _ _~

]978 UNIT *NAME: Salem #1 DATE: August 10, 1978 COMPLETED BY! _..:_L..:_._K_;:_.=Mi=-'_1_1....:..e_r_=--=

TELEPHONE: 609-365-7000 X507 ME'nDD OF I OORATIOO SllUITIOO LICENSE SYSTm CXl1POOENl' CAUSE AND (l)RROCTIVE NO. DATE 'l'YPEl (llXJRS) RE1\SON2 ro'IN E.'llllfl' CXlDE4 CXlDES ACTION 'ID RFJ\C'IOR REPORI' I PREVENJ.' REnJRRENCE I

78-85 . 7-17-78 F 0 A 4 - - --

i.

HH Filter Clean 12 Heater Drairi Purrp Suction Strainer.

78-86 7-18-78 F 97.36 A 3 - - - - EB Transf. Reactor Trip Due to Under Frequency i ' on 4 KV Group Buses lF and lH.

I .

J 78-87 7-22-78 F 0 A 4 - - - - HH Filter Clean 11 and 13 Condensate Pump i* Suction Strainers.

78-88 7-22-::-78 F 0 A 4 - - -.. - HH Filter Clean .12B Circulating Water Screen"

\

~ I~

78-89 7-24-78 F 0 A *4 - - ... - HH Filter Clean ..Condensate Pump Suction

!. Strainer *.

'i:

78-90 7-25-78 F 0 A 4 - - -ii - HC HTEXCH llA Condenser Leak.

78-91 7-25-78 F 0 A 4 -- '

i'

~ HH Filter Clean 11 and 12 Stearn Generator Feed

' Purrp Suction Strainers.

I I

78-92 7-26-78 F ' 0 A 4 - - HC HTEXCH llA Condenser Leak.

Page 8 of 23 B-1-7.Jt ,

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UNIT SIIDI1XMNS AND ~ ~IONS DOCKET NO. : _--;:;-s~o.--_2_1..,,2~---'-'

~RI' rq.mi  ; July, '.1..978 UNIT *NAME I Salem #I '.

I DATE: August 10, 1978 1

.i COMPLETED BY: L. K. Miller

.. TELEPHONE: 609-365-7000 X507 ME:l'HJD OF '

OORATIOO SIRJlTIOO Llcm5E SYSTEM CiltPWEN1' CAUSE AND mRROCTIVE TYPE1 RFA50N2 i

00. DATE (OOURS) ram EVENr. CDDE4 CDDES ACTION 'IO RFJICIDR REPORr I PREVENI' REOJRREOCE i

78-93 7-26-78 F 0 A 4 - - - - HF Filter 12B Circulator Screens Clogged.

I 78-94 7-27-94 F 0 A 4 - - - *- '*

HC HTEXCH llA Circulator Condenser Leak.

i 78-+95 7-27~78 F 0 A 4 - - -- HH Filter Clean Condensate Pump Suction

. Strainer

  • J i

78-96 7-28-78 F 0 A 4 - - - .- RC xxxxxx

  • Xenon Oscillations 78-97 7-29-78 F 0 A 4 -' - RC xxxxxx Xenon Oscillations 78-98 7-29-78 F 0 A 4 - - ;.- RC xxxxxx Xenon Oscillations 78-99 7-30-78 F 0 A .4 - - - - RC xxxxxx Xenon Oscillations78-100 7-31-78 F 0 A 4 - - ~ - HH Filter Clean Steam Generator Feed Pump

' Suction Strainers.

Page 9 of 23 8-1-7.B" *.

. -~ \_)

MAJOR PLANT MODIFI~TIONS DOCKET NO: 50-272

---~-=-.t..=.--------~--~~-

~PORT MONTH Ju., 1978 UN I T~E: Salem I

--"'"-='-==-=----------------

DATE: .August

. 10_, 19 78 COMPLETED BY: L.. K. Miller TELEPHONE: {609) 365-7000 X507

  • DCR NO. PRINCIPLE SYSTEM SUBJECT ED-0058 Main Steam Piping Modify Turning Vanes ED-0143 1A-125VDC Battery Change cells 2, 8, 36, 50, & 56 ED-0*143 1B-125VDC Battery Change cells 7 & 47 ED-0160 Fire Protection Relocate C.R. Fire Detectors ED-0169_ Station Power Install Wattmeter Transducer on SPT and Aux. Transformer ED-0364 Service Water Install Modified Service Water Pumps. 11, 15, & 16 completed.

l_:EC-0378 Condenser Install Experimental Tubes.

1.;..EC..-0385 Diesel Generators Install Modified Turbochargers

  • DESIGN CHANGE REQUEST 8-1-7. Rl PAGE 10 of 23

DOCKET NO.: 50-272 MAJOR PLANT REPORT MONTH MODIFI~IONS

. JulJIJ' 1978 uw NAME: Salem I August 1.0 ,1978 DATE:

COMPLETED BY: L. K. Miller TELEPHONE~(609)365-7000 X-507

  • OCR NO. 10CFRS 0. 5 9. SAFETY EVALUATION EC-0058 Functional operation is unchanged. The design change will improve reliability. The basis of the technical specifications are not affected.

ED-0143 Change of battery cell external connections in no way alters the capacity or perfGlrmance data listed in the SAR or Technical Specs.

ED-0160 Not Safety Related and does not effect any safety related systems.

ED-0169 Safety related equipment will not be affected.

ED-0364 A revised seismic analysis has been done on the new aluminum bronze column pipe. The impeller modification produced a flatter head-capacity curve without affecting design flow point.-. System still performs original. design function.

Probability of accidents has not increased, nor has the oecurrence *-- of new accidents been made possible. The Tech.

Spec bases are unaffected.

l-EC-0378 The modification of this system does not affect any presently performed safety analysis nor does it create any new hazards.

The basis of the technical specifications are not affected.

l-EC-0385 This modification is being made to reduce the potential for further failure-of the Emergency Diesel Generation turbo changers. This modification will not reduce the margin of safety in any Technical Specification;* cause an accident or malfunction not previously analyzed in the FSAR, nor increase the probability of occurrence or consequence of such an accident.

Pg.11 oif 23

DOCKET NO.: 50-272 UN-NAME: Salem #1 su~.IARY OF SAFETY REL~ .MAINTENANCE DATE: August 10, 1978 DEPARTMENT Maintenance COMPLETED BY: L. K. Miller REPORT MONTH July, 1978

~ TELEPHONE: 609-365-7000 X507

(~l WOEL~ ORDER EQUIPMENT FAILURE-DESCRIPTION CORRECTIVE ACTION

~0-i OD-9215 Valve I2SW24 Valve leaks through. Replaced diaphragm. I OD-9199 Valve 13RC:l6 Packing leak. Tightened packing nut. .

OD-9027 Valve 1CV2 Flange leak. Replaced bonnet and seat gasket.

OP-0280 lC Dieser Gen. Replace with rebuilt unit. Replaced unit~

Turbo *charger. --------

f) OD-8160 Valve llMS17.l Packing leak~ Repacked valve.

OD-9253 #11 Chiller Freezes up. Recharged unit.

OD-8814 lC.Diesel Diesel trips on over crank Lubricated ~Governor Linkage.

OD-8143 15 Service Water Lbes not purrp. Replaced Purrp.

Purrp.

OD-9366 #11 and #12 Heat trace__circuit,in !Replaced tenp. sensing elements.

toncentrate Purrp alann condition.

OD-8498 Ul Chiller Co:rrpressor Short Cycles and Replaced Mechanical Seal Compressor trips on freeze protect.

(

.>---:~ OD-8961 fJalve 11SW24 Ruptured - .....diaphragm Replaced diaphragm.

'd} *_Page

<f 12 of 23

.. 1 8-1-7.Rl

DOCKET NO": 50-272 Salem #1

. ~u~~~Y OF SAFETY RE.emINTENANCE u'rE:

' DATE: August 10, 1978 DEPARTMENT Maintenance COMPLETED BY: L.K. Miller REPORT MONTH Jull, 1978

.f\ TELEPHONE: 609-365-7000 X507

('- . I!

_J~

woR*K ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION I I

NO. '

OD-9363 #15 Service Water Drive noter shaft gland Repacked strainer.

Pump Strainer. leaks.

00-8698 le Diesel Pipe leak. Replaced pipe cap.

OD-8475 le Diesel 11 Start Air Compressor Tightened head bolts.

head leaks.

OD-7435 11 Chiller Inadvertant trips*--*-- Charged #11 Oriller *.

r OD-9048 #15 Service Wtr.

  • Pl.JllP.

Pump leak. Installed new pump.

.MD-2805 1A Diesel Jacket water heater. Recalibrated TD-7343 failure alann *.

MD-2810 le 4KV Vital Bus Under voltage.relay fail- Recalibrated relay.

ed to m=et Tech. Spec.

OD-9303 1A and B 125V. Voltage too high. I..owered voltage to*correct level Batteries.

OD-9301 28 VOC Battery Voltage too high Calibrated voltage meter.

Charger.

OP-0312 #15 Service Wtr. Replac;::e purrp* IAI.il DCR:* .. Installed Pl.JllP*

Pl.JllP. ~0364-15. -~ .

~QD-,8529 Valve lll-JT22 Leaks at threaded connec-* Replaced gasket.

tion. ......... -

'--i

  • Page 13 of 23 8-1-7.Rl

,0'17Q"'\7CT'!K<1E:;><TT"IN~OT.- *:-- --- ~72 ----

U~~E:~S_al_em~#_l______~--~

, S.U~~y OF SAFETY RE~rINTENANCE

}'"MTE: August 10, 1978

. DEPARTMENT

  • Mal.Iltefiance REPORT MONTH July I 1978 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 (91~~----'------.----------r-------------..----------------1 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OP-0313 #16 Service Water Replace punp OCR ED-0364- Replaced pUilp.

Pump 16.

OD-8869 #16 Service Water Flex line on sealing water Replaced flex line.

PUilp to stuffing box leaks.

MD-2813 Valve 11SW24 Diaphragm leak Replaced diaphragm.

I

  • MD-2677 lB Batte.?:y
  • Replace cells as pei Replaced cells.

--"--~--

OCR ED-0143. -- -----**-

J OP-0308 #11 Service Water Replace Pump as per Replaced Pump 8-PUilp.

- OCR ED-0364-11.

MD-2676 JA Batte.?:y Change cells OCR ED-0143 Replaced cells.

MD-2814 #1 Unit Cast Repair cable take up reel. Rewound reel.

Handling Crane.

MD-2168 #12 RlIR RoOL-n Cooler Pipe leaks. *Replaced pipe.

0 Page 14 of 23 8-1-7. Rl

DOCKET NO.: 50-27~

Salem #1

. ~U~~y OF SAFETY REL~~INTENANCE August 10, 1978

. DEPARTMENT Perfornance L. K. Miller REPORT MONTH July, 1978 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-9355 APD Unit No ItDtion*in filter drive Changed filter screen.

sys-cem.

PD-4882 1PC948A/D- High output. Adjusted setpoint.

PD-4888 #11 IDop AT/TARG *Out of spec. Calibrated~

PD-4896 llC106A,B, & C. 0ut of spec. Adjusted setpoints.

PD-4897 Rl'.18 *lRlB Detector problem. Replaced detector tubes.*

OD-9291 #ll Accumulator *Ievel Chan. "A" erractic, Replaced strain gauge on Indic. "Sticks"

  • transmitter repaired and call~,:

brated indicator.

OD-9260 #11 Accum. Chan.A Irtcreas;ing level while Replace strain_gaµge on Chan. B is constant. transmitter repaired and calibrated indicator.

OD-9117 Accumulator *Calibrate 11 and 12 Recalibrated 934A, 935A, 935B, Accurmilator Level. 934B.

OD-9395 Pressurizer revel Ievel Channels *ai1 indicat Conpound Bezel reading

  • . Channels. di.ff adjusted to orginal voltage.

OD-9201 _ RMS lR-13-C Inlet & outlet valves do Calibrated.

~--

not operate.

\

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Page 15 of 23 8-1-7.Rl

.SU.MMf..RY OF SAFETY REL~~INTENANCE u!-1A*:*1'*E

  • ~
___s_al_em_#_l_ _ _ __

_DEF ARTMENT Perfonnance D TE: _ _A_u_g_u_s_t_*_l_0_,_1_9_7_8_ __

REPORT MONTH July, 1978 COMPLETED BY: __L_._K_._Mi_'l_l_e_r_ _ _ _ __

J/°\. TELEPHONE: 609-365-7000 X507

('-e-,r-*A.._ _ _ _r - - - - - - - - . - - - - - - - - - - - . - - - - - - - - - -

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-9068 #13 Aux. Feed No start indication in Adjusted limit switch.

Water Purrp. control room.

PD-4862 lFT-513 Verify operation. Recalibrated.

PD-4524 llSGFP Turbine Determine cause of Modified speed control circuit osa:illations. corrected by OCR FC0380.

RE-131 AFDM Reset target 11T TO -3.7% Target 11T Set to -3.7%.

OP-0359 RMS RllA Reset alann according to Reset RllA trip point.

DCR EC-0390.

Spare RMS Recorder Recorder.not printing. Repiaced *clutch and -cleaned -

contact.

OD-9202 11 Fan Coil Unit Roughing filter indicator* Opened ciir supply to solenoid.*

Filter. shows closed.

OD-9259 EH Speed Reference Channel failed. Replaced carnparator.

Channel.

PD-4869 llC548C Low Level 14 SG Channel::rr Replaced capacitors.

"tripped intennittedly.

PD-4878. 11 Steam Gen. Intennittent Il:Jw-IJ:Jw Level Replaced Capacitors-and adjust-Level. partial trip on computer. ed output volts to lllVAC.

PD-4646 #13 Stop Valve. Lirnit switch is not open. Oiled roller and switch~

.!/~ PD-4835 Status Panel =~ ~~~~in~n1!:~~ ~~a~an:1c~p~e1: rf~;;.

(,_ 1_. - - - - - - - - - - - - - - - - - - 1 1 _ *g_h_ts_*_w_er_e_e_f_f_ected

_ _*_ ___.._ _ _ _ _ _ _ _ _ _ _ _ _ _ ..A-Page 16 of 23 8-1-7.Rl

- DOCKET NO.: 50-272

,SUMMKRY OF SAFETY RE~~INTENANCE

.DEPARTMENT Perfo:anance U*t:E: TE:

Salem #1 August 10, 1978 REPORT MONTH July, 1978 COMPLETED BY: L.K. Miller

/\ TELEPHONE: 609-365-7000 X507

('-.jl t'10RK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

PD-4876 1BS948B Set point drifts. Installed new :rrodule.

PD-4872 1BS457B out of Spec. Reset set point.

PD-4870 Rx Prot *. Terrp alarm did not clear Replaced power supply capacitO:r:..

Console Alarm after functional test.

PD-4865 RMS 1Rl3C With detector disconnected, Replaced alann :rrodule.

high alarm is on.

PD-4861 1Fr512 Verify oper:ation of Functionally checked.

transmitter. ..

Ir" \ -- *- *- ... ..

  • (J-. -

PD-4858 llSG Chan. II Verify operation of steam Functionally checked.

Steam Flow. flow Channel II.

PD-4857* llSG Stin. Flow Verify operation of steam Functionally checked.

Channel I. flow Channel I.

OD-9240 Reactor*Coolant Alarm canes up without 3° Replaced power supply capacitor *.

TAVG-TREE' Alarm

  • Deviation.

OD-9154 14 Steam Level deviation alann for Replaced capacitors on lIM-505-E Generator Level. no apparent.reason.

OD-9077 . Valve llMSl 71 ValVe leaking~ Stroked valve.

OD-8943 Pressurizer Alanred at 330 PSI Perfonned channel calibration.

l Press~ Ch. I .*

~** 1OD-8930.

  • ~

PT403 Control Room Indicator Calibrated surrmator.

  • reading incorrect.

Page 17 of 23 8-1-7.Rl

-- SALEM I OPERATING

SUMMARY

JULY, 1978 7-1 At 0350 a load increase from 70% was started. The unit reached 90% at 0636. At 0941 an E-H System Failure Alarm was received, reactor power dropped 8% and the alarm cleared. The E-H System was _placed in manua~-control. A load reduction was started at 1050 in order to clean condensate pump suction strainers. At 1500 a load increase was started from 63% power. At 1625 with the E-H System in manual, the controller failed high. Reactor power jumped 12%-and was finally stopped by the turbine governor valve position limiter. A load reduction was then initiated using the valve position limiter to lower the load. At 2233 the E-H System failed low and the governor valves went closed.

The operator manually tripped the reactor.

7-2 The reactor was taken critical at 0057 and the unit was synchro-nized at 1344. Reactor p-ower- was""' then increased and reached 64%

at 2400.

7-3 The Load Dispatcher placed emergency minimum loading into effect

  • I I

at the request of the PJM interconnection. The unit output was I limited to 50%. At 0545 the emergency minimtlm loading was cancelled and the unit began a load increase. Power was increased to 70%

and held to clean a condensate pump suction strainer. At 1036 a load decrease was started to reduce power to 50% to clean a feed pump suction strainer and repair a feed pump recirculation valve.

Power was held at 50% the rest of the day.

7-4 At 0825 the load dispatcher requested a load increase from 50% to 70%. The unit reached 70% at 1535 and remained here the rest of the day.

Page 18 of 23

7-5 At 0212 a load increase was started to 100% power. At 1435 power was decreased to 90% to clean a heater drain pump suction strainer.

At 1700 a load increase was started to 100%. At 2130 a load decrease to 70% was started to clean a condensate pump suction strainer.

7-6 At 0407 a load:*_increase was started to 100%. Stablized reactor power at-approximately 99% for the remainder* of the day.

7-7 Reactor power stabilized at 99%. At 1125 load was reduced to clean. .he.ater drain pump strainer. At approximately 1300 reactor power at 90%. Strainer cleaned and load was being increased to 100% at 1320. Reactor power was at 100% at 1630. Load was reduced from 99% to 90% to clean heater drain pump strainer at 20,45. Load was at 90% at 2230. At.2245 load was increasing to 100% ~fter HDP strainer was cleaned.

7-8 Load was increasing to 100% from 94%. At 0140 reactor power i~

- --\- *-*-**- -* - .... - ** __ . - - .-.-* - ..- . -* .. --

99. 5%. At 0245 reactor power was decreasing from 99.5% to. 90% to clean heater drain pump strainers. Reactor power was at 90% by 0415.

Heater drain pump was returned to service and increased load to 100% at 0425. -Reactor power was 1,007 at 0613. Load was decreased from 99.5% to 90% for heater drain pump maintenance at 0915.

Reactor power was 90% at 1115. Heater drain pump is put in service and reactor power is restored to 100% at 1130. At -1400 reactor power is 100%. At 1500 load is reduced from 99% to 70% to clean condensate pump strainer. Reactor power is at 70% at 1900. Strainer is cleaned load ~s increasing to 100% at 2145.

7-9 Load is at 74% and increasing to 100%. Load is at 99% at 0400. At*

a525 load was decreased from 99% to 90% for maintenance on heater drain pumps. ..Load was. at 99 % at 0605. HDP was put in service and

  • load was increased from 90% to 100% at 0630.
  • ~-......._ - ....

Page 19 of 23

7-9 Load increased to 94% at 0655. Load was decreased to 90% from 94%

due to heater drain pump cleaning at 0750. Load was 90% at 0850.

Heater drain pump is in service and load was increased from 90%

to 100% at 0945. Load is 99% at 1200. Load was reduced at 1535 for heater drain pump maintenance from 99% to 90%. Load was 90%

at 1657. Load remained at 90-92% for the remainder of the day.

7-10 .Reactor power was at 91% due to cleaning of heater drain pump maintenance. Load was increased to 100% at 1745 from 91%. Load was being held at 96% at 1830 to watch feed pump strainer D/P.

At 2200 commenced decreasing. load to 50% from 96% to clean feed pump strainer.

7-ll Load is at 52% at 0400. Strainers were cleaned and load is increasing to 100% at 0540. Calorimetric taken at 1110 at 87%

power~ Reactor power at 99.5% at 1600. Decreasing load from 99% to 90% at 2300 for heater drain pump strainer cleaning.

7-12 Coming down in load to--ciean___ heater drain pump strainers~ Power stabilized at 90% at 0030. The heater drain pump was* returned to service and load was increased from 91% to 100% at 0350. Load was at 100% at 0545. Load was reduced from 99% to 90% at 2140 for heater drain pump maintenance. Load stabilized at 89% at 2350.

7-13 The heater drain pump was returned to service and load was increased from 92% to 100% at 0625. Load was reduced at 2145 from 96% to 90% to clean condensate pump strainers.

7-14 Load at 0300 was at 70% to clean condensate pump strainers. Strainers were cleaned and power was increasing at 0600 from 71% to 100%.

Power was greater than 97% between 1-100 and 2130. Power was greater than 97% between 1100 and 2130. Power was decreased for #12 heater drain pump strainer cleaning. At 2255 power was at 90.5% and return-ing to full power.

Page 20 of 23

7-15 Power was increasing to 100% from 95%. Power was greater than 95% until 2210. Power was decreased to 50% to clean feed pump strainers.

7-16 Power was. at 50% at 0530 *. Strainer was cleaned and power was increased to 100% at 0600. Power was greater than 95% from 1320

  • -- through the remainder of the* day.

7-17 Plant power was being maintained greater than 95%. Reducing power from 99.5% at 2210 for maintenance on #12 Heater Drain Pump. Power was reduced to 93% at 2335.

7-18 Power was increased from 93% at 0001 to 100%. Reactor power was greater than 97% from 0110 to 0657. A reactor trip occurred at 0657 due to under frequency on group buses, causing all four (4)

RCP's to trip. Prior to the trip the power level was 98.2%.

Reactor was shutdown for ~h~.r~mainder of the day.

7-19 The plant was shutdown. Commencing of cooldown started at 0600 for minor plant maintenance activities. The reactor coolant system was 390°F. at 1100 for repairing of leaking check valve 1CV78 .

. Commencing heatup of the plant at 1500.

7-20 Preparations being made for plant startup.

7-21 Reactor was critical at 0430. Boron was 974 ppm and rods were at 156 steps on Bank D. Turbine was syncronized at 1045. A power increase was started and the unit reached 93% power at 2400.

7-22 The unit reached 100% power at 0100. At 0300 a load reduction to 70% .was started in order to clean condensate pump suction strainers. The unit returned to 100% load at 1418.

Page 21 of 23

7-23 --

The unit operated at full load all day.

7-24 The unit operated at full load* until 2148 when a load reduction to 70% was initiated to clean condensate pump suction strainer.

7-25 The unit returned to full load at 1100. At 1700 a load reduction to 50% was initiated to clean feed pump suction strainers.

7-26 The unit returned to full load at 0830 and operated here the remainder of the day.

7-27 At 0700 load was reducted to 94% when it was observed that the margin to trip for the overtemperature ~T trip was reduced. It was later determined that a loose wire in a controller was the cause of the decreased margin. The unit operated at full load until 2138 when a load reduction to 70% was initiated to clean condensate pump suction strainers.

7-28 '!'.be unit ~eturned to full power at 0.748 and re"fnained at full

  • load until 7-31.

7-31 At 2108 a load reduction to 50% was started in order to clean feed pump suction strainers.

Page 22 of 23

.. REFUELING INFORMATION DOCKET NO.: 50-272

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

UNIT: Salem No. 1 DATE:

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

COMPLETED BY: LoK. Miller TELEPHON~:609-365-7000 EXT. 507 MONTH:~~J_u_l~y~,--1_9~7_8..._______________~

l.o Refueling in-formation. has changed from last month:

YES ---NO _ X

2. Scheduled date of next refueling: April l, 1979
3. Scheduled date for restart following refueling: May 29, 1979 4 0 A. Will Technical . Specification changes or other license amendments be required? YES NO _ ___

NOT' DETERMINED TO-DATE July, 1978 B * . *Has. the reload fuel. design been reviewed by the Station Operating Review Committee? YES NO X If no, when is i t scheduled?. January, 1979

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

5. Scheduled date(s)" for submitting proposed licensing action:

February, 1979 if required.

6. Important licensing considerations associated with refueling:

None

7. Number of Fuel Assemblies:

193 A. In-Core B. In Spent Fuel Storage 0

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:
  • April, 1982 Page 23 of 23
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