ML19031A352

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Submit Operating Report for Month of September 1978
ML19031A352
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/10/1978
From:
Public Service Electric & Gas Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML19031A352 (15)
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Text

{{#Wiki_filter:IXJCKET NO. 50-272 UNIT Salem #1 DATE October 10, 1978 COMPLETED BY L.K. Miller TELEPHONr: 609-365-7000 X507 MONTH September., 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER Ll::VEL (MWe-NET) (MWE-:NET) 1 1066 17 1084 2 1052 18 1087 3 1062 19 1077 4 1078 20 1089 5 1073 21 1089 6 1095 22 1077 1055 0 7 23 1066 20 8 24 g 980 25 0 1093 614 10 26 11 1113 27 231 12 1022 28 . 505 13 1072 29 661 14 1076 30 809

15. 1131 31 16 1065 Pg. 2 of 16 8 .1-7. PJ.

18'1ot.bDCJ9o

r:x:c:ET ro.: 50-272 CM'E.: October 10, 1978 

                                                                                                           ~ SY:               L.K. Miller
                                                                                                                ~:.          609-365-7000 X507

. l. llait Naaa:. 2. 3. P.epaz:t:inq Pe:icd: I icensed ~ Salem #1 September, Power.: (Mit}: _ 1978 __,3_3_3_8_ _ _ _ __

4. Nama!p.late Rat:i.Dq . (Gl:css. MNal : _ _ 1_13_5_ _ _ _ __
. S*. Design: !lertrirnl ..Ra:tm;; (Net::.MNa):      _....;;l;;.;:0-.9.;;.0_ _ __

6 *. Max=!xmmCependable:capacity (Gl:css.*Kfel :_*_1_*1_2_4_ __

7. Maximin* nepoondable*capad.t'/* (NetMNa~: _.,...1... 07_9.___ _

a.. If °'an;JPS Oc:cm: in Capacity Pad:Jt;s:: (Il:em Nulli:ler- 3 ~ n Since Last: R.epott *. Give* Reascn: None This*~ Yeartc Date 720 6551 10,992 ll. Ei:nIJ:3 In Rep:t:i.nq Pe:io::1. 12- NmD!r. Of Hcurs Read:cr' was Critical. 663.6 3921.4 6,464.6

13. P.eactcr* ReServe Shlltxbm. lblrs. 0 0 0 14..
  • Hours Generator on-til'la 657.9 3726.9 6,157.5 IS. Onit Peserve*Shut:dcwn*Hcc:rs 0 0 0 l5. . GJ:Css .Tberma 1 . Ecergy Ge:a!:ated (MtiH) *1,988;978.4 11,146,972.6 17,842,192.6 17~ ' Gress Elect:d.cal Energy GeDerated (ME) . 660,!60 3,744,sio 5,930,820 lS. Net El.ect:::!.cal. ~ ~(?>H!) 630,269 - 3,549,560 5,607,778 1.9. Onit Se:vl.ca. Factor* 91.4 56.9 56.0 20:. Onit Availabil'ity Factor 91. 4 56.9 56.0 2l. On:it capa.c:ity Factcr. (Us:illq MOC. Net) 81.1 50.2 . 47.3
22. Oni.t capacit'] Factcr* (C's:inq CER Net).. 80
  • 3 49.7 46.8 23 *. Onit: Forced 01%tage Rate 8. 6 43.1 34.07
24. Shatdcwns.Scheduled ~Next s* Martbs. riwe. Date, am OUraticn of Eadll:
                *Unit Refueling 3/31/79 - .5/26/79 25~     If Sbut. Down At Eccl o£ Rep:lrt Pericd~ Estimated. Date of St:art:IJP: _N_/_A                  _ _ _ _ _ _ _ _ _ _ _ _ __
  • 26. Oni.ts* In.Test Statcs(Prior tc.Comerc:ial ~): *-.

Forecast kh:l.eved 9730/16 12/11/76 11/01/76 12/25/76 S-l-7.R2 Pq. 3 of 16 12/20/76 6/30/77

UNI1' SllU'l'ln'/NS NllJ IU-W.R REIXJC'l'la-IS DOCKET NO.: 50-272 REOORT MJNnl Sept. 1978 

                                                                                                                                           ~~~~~~~~-

UNIT NAME: Salem #1 DJ\'l'E: October 10, 1978 COMPJ,ETED Dy: L. K. Miller TELEPHONE: 609-365-7000 X507 MlmOO OF OOMTION SlllJITIOO LICDISE SYSTEM ~ CJ\USE l\ID CXlimocTIVE

00. DATE TYPEl (Irons) ~: cxw EVl!Nl' CXlDE4 CXllJE5 1\CTIOO 'ID IU!'.l\C'roR REPoRT I PREVml' RIUIRRl:"?O:

78-181 78-214 9-9 9-23 F F 62.1 0 (A) (A) 4 (A) 3 HH HH FILTER PUMPXX Clean Condensate Pump Suction Strainer Reactor Trip Due to Failure of #13 Condensate Purrp. 78-221 9-26 F 0 A 4 (A) ----- HH PUMPXX Failure of #12 Condensate P~. 78-222 9-26 F 0 A 4 (A) HH PUMPXX Inspection of #13 Condensate Pump LchTer Bearing. 78-223 9-26 F 0 A 4 (A) ------ HH PUMPXX Inspection of #11 Condensate Pump*' Lube Oil. 78-224 9-28 F 0 A* 4 (A) ------ HH PUMPXX Inspection of #13 Condensate Pump raver Bearing~*. 78-225 9-29 F 0 A 4 (A} --~--- HH PUMPXX Check #12 Condensate Punp Alignnent. 1 2 3 4 5 F: Forced Reason: Method: Ellhlbit G - lnstructions Exhibit 1-S<me S: SC'heduled A-Fl:juiprent Failure (Explain) I-Manual for Preparation of Data fiource 

                              &-Maintenance or Test                                 2-Manuai Scram.              Entry Sheets for Licensee C-Refueling                                             3-Autanatic Scram.          Event !Eport (LER) File.

D-Regulatory llestricUon . 4-0ther (Explain) (trunm-0161) E-{\>erator Training & License Examination F-1\dmlnistrative A. WAD REDUCTION. 8-l-7.R2 G-Operational Errot(Explain) Ii-Other (Explain) B. CONTINUATION OF PREVIOUS ourAGE. Pg. 4 - of l'.6

UNIT Sfll1ltnlNS AND IWER REIXJCTIONS DOCKET NO.: 50-272 

                                                                                                                               --------~

REPORI' MJJmt September, 1978 .. UNIT 1NAME: Salem #1 DATE: October 10, 1978 

                                                                                                            -COMPLETED PY: _L_._K_._Mi_'l_l_e_r_ __

TELEPHONE: 609-365-7000 X507 ME'IUJD OF ruru\TICN Slfl1ITIOO LICENSE SYS~ CXJ.fPOOENl' CAIJSE AND CDRRI'n'IVE N'.J. DATE TYP~ (IPJURS) REl\5002 ~ E.VENI' CDDE CDDES. ACTION 'IO RFJ\C'OOR REPORT I PREVENI' REOJRRENCE 78-228 9-29 F 0 A 4(A) ------* HH PUMPXX #11 Steam Generator Feed Purrp 

                                                                                                . Vilirations.

78-229 9-30 F 0 A 4 (A) ----- ~ PUMPXX #11 Steam Generator Feed Purrp

  • Vilirations.

78-232 9-30 F 0 A 4 (A) ------ HH PUMPXX #11 Steam Generator Feed Purrp " Vibrations

  • 78-233 9-30 F 0 A - 4 (A) ----- HH PUMPXX #11 Steam Generators Feed Ptimp Vibrations.

I 

                                                                     *,i
I Page 5 of 16 B-1-7.Rl

MAJOR PLANT MODIFiilTIONS 

                                                     ~T NAME:           Salem #1 RE;ORT MONTH       sept!lber, 1978 DATE:        OctoberlO, 1978 COMPLETED BY:~_L_._K_.__M_i_l_l_e_r____~

TELEP HONE : ( 6 0 9) 3 6 5- 7 0 0 0 X5 0 7 

        *DCR. NO.         PRINCIPLE SYSTEM                       SUBJECT ED-0110       Control Rod Drive Vent Fans. Various Structural Improvements.

ED-0281 Circulating Water Install Entrainment Sampling Pipe. ED-0364- Service Water Installed Modified No.13 Pump. 13 l.-EC-0399 RMS ( l-R-8) Setpoint Change. OD-0011 Component Cooling Header Alarm Setpoint Change. 1* 7. Page 6 of 16

  • DESIGN__CBANGE REOilEST

MAJOR PLANT MODIFICATIONS REPORT MONTH Septen& I 1978 IIT NAME: Salem #1

  • DATE: October 10, -~1978 COMPLETED BY:~_L_.__ K_._Mi_*_1_1e_r_______

TELEPHONE: (609) 365-7000 X507 

   *DCR NO.                              10CFRSO. 59;                          SAFETY.'.EVALUATION ED-0110             An             unreviewed safety question is not involved.          Safety related equiprrent will not be affected.
  • ED-0281 An unreviewed safety question is not involved. Saftey related equiprtent will not be affected.

ED-0364 A revised seismic analysis has been done on the new aluminum bronze colutm pipe. The impeller m:xlification-produced a flatter head~capacity ~ without affecting* design fle7N point. System still performs .original design function. Probability of accidents has not increased, nor has the occurance of new accidents been made ~ssible. The Tech. Spec bases are unaffected. lED-0300 This rronitor*and its 'setting dees*nbt affect.the* safe* operation or shutdown of the plant. OD-0011 The Design Change alters a non-safety related function of a circuit which is otherwise safety related. The Safety related functions of the circuit remains unm:xlified. The new design has been reviewed and dete:rmined not to create new potential rralfunctions or increase the probability of previously arialyzed malfunctions or accidents * 

                                                                                         .LO.'::jO::: I U.1.. .LU L   --------* . . . . . . . . . . . . ~-  _ _ .,.. ____ ,..,,,, -------

__j

DOCKET NO.: 50-..:1..: 

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

SUMMARY

.' OF SAFETY RELA~ MAINTENANCE UN-NAME : _ _s_al_em __#_l_ _ _ _ _ __ 

                              .perfonnance                                             DATE:         October 10, 1978 DEPARTMENT REPORT MONTH September, 1978                                  COMPLETED BY:          L. K. Miller TELEPHONE:      (609) 365-7000       X507 WORK ORDER        EQUIPMENT                   FAILURE DESCRIPTION                     CORRECTIVE ACTION NO.

PD-4967 Reactor Coolant Recalibrate 12 Reactor Calibrated. System Coolant Loop to new /::,,T/Tavg values. PD-4964 1BS532 1FC532 out of spec. Repl~ed isolator and cali-

  • brat
  • PD-4966 lBSSlOA Console alann failed to Repaired comparator.

reset. OD-9968 #13 Steam Generat01: High differential level Recalibrated. bet.ween Channel N and 

                                    -        other channels.

PD-4969 Reactor Coolant Recalibrate 13 Reactor Calibrated. .. System Coolant Loop to new l::,,"f:/Tavg Values. PD-4973 1BS541B Out of spec. Calibrated.* PD-4'974 Nuclear Instru-'.". N43 isolation anplifier* Calibrated. *, nerttation System out of spec~ P0-:4989 Air Partibulate *rnvestigate *filter *-. Replaced* filter paper and Detection Unit failure. alann. charcoal filter. Repaired c~stan shear pins. OD-10441_ Valve 13AF11 No closed indication. Adjusted limit switch. PD-5057 Reactor Protection Recalibrate l'IC-505 for Calibrated. new Tavg program. PD-5058 Reactor Protection Recalibrate lPI'"'."505 and calibrated. lPT-506. OD-9084 #12 Steam Generatm I.Dll Channel III' pressure Perforrced calibration check. indication. 

                                                           **~ .:*~,

OD-9295 Valve 1SW169 Failed open. Replaced control air supply solenoid valve SV598 *. Page 8 df 16 8-L-7 .Rl ---

DOCKET. NO * : :JU-~/~ UN-NAME: Salem #1 SUMMA.Ry' OF SAFETY RELA& MAINTENANCE. OEP ARTMENT Perfonnance DA".['E: October 10, 1978 REPORT MONTH September, 1978 COMPLETED BY: L. K. Miller TELEPHONE.: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAlLtJRE DESCRIPTION

  • CORRECTIVE ACTION NO.

OD-9562 TL6339 .Erroneous reading. Tightened packing nut on 

                                                                                     ..                  root valve
  • OD-9920 RMS 1Rl7A Channel alarm sounded. Detection tube cleaned and channel functionally checked.

OD-9934 Refueling Water Erroneous high level over- Calibrated level transmitter. Storage Tank head. annunciator alarm. OD-9966 #11 Steam Gez:iera- High differential pressure Calibrated *. tor bet.Ween Channels I & II. OD-9986 #12 Service Back wash malfunctions . Strainer gages recalibrated *. Water Pump in... auto mDae. *- 

                    -*                                      *- -r.-                -                                                           -

OD-10009 Air Part:.:i.culate . IJ:M*flow operation. Gas i?uriP-i-e}?1aceci

  • 6*

Detection Unit ' PD-4836 ll.Cl02C out of .spec. calibrated *. i 

   .
  • PD-4958 -'.Nuclear* **rnstru- Channel N44 *NC307 'Bistable . , Replaced bistable.

rrentation System malfunctioning *. PD-499.0 Control Bank A Investigate alarm. Replaced fuse. OD-10330 #13 RCP Channel II Channel out of adjustrrent. Recalibrated. OD-10389 1CV172 Valve No open indication. Adjusted limit switch. OD-10134 Shutdown.Bank A Urgent alarm sounded. Replaced fuse F3 on rrovable grippes

  • PD-5053 1TE43JA/B lBS432C and lBS432D are Adjusted gain and bias l'le432C/D out of spec. of l'IM432A .
                                                                              -~-

OD-8166 #11-14 Stearn Mismatched readings between Calibrated 1.FI'532. Generators steam flow and F.W. flow. Calibrated 13&14 Steam Flow Page 9 of lfr and Feed Flow recorder & Isolate:::: 8-1-7.Rl

SUMMARY

. OF SAFETY RELA~ MAINTENANCE DOCKET. NO . : UN - --------------- 50-272 NAME: ___s_ai_ern_#_l________ DEPARTMENT. Maintenance DATE: ___..q_c~t~o~h~e~r.._1~0.._. 1 _1_9~7-8...____ REPORT MONTH September, 1978 COMPLETED BY: L. K. Miller TELEPHONE: ----------------------~ (609) 365-7000 X507 WORK ORDER .EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. OD-10281 #12 Service Leak at bottom of strainer Repaired leak by patch weld. Water Punp OD-10357 Boric Acid Leak on condenser head. Replaced plug and tightened Evaporator boltse OD-10363 #11 Service Leak in upper bearing Replaced cooler. Water Punp cooler. MD-2966 #11 thru 15 Weld couplings to rrotor Complete. Fan Coil Units cdoler nozzles. OD-8722 #13 and #14 Will not run in auto. Dried and sealed motor lead Residual Heat ... terminations. Renoval Sump Punps -. - . - -* OD-10052 #12 Residual overhead Annunciator Rercoved ground and repaired - - Heat Renoval Alann on. level switch. Sump Punp i MD-2441 Valves 1CV2, 5, Boric Acid around packing. Repacked. 75, and19. OD-10447 Valve 1CC131 Valve will not close Replaced Aux. contact * 

                                        .electricity.

OD-10381 #13 Control Area Auto roughing filter Repaired control and replaced Supply Unit advance control inoperable. filter. Filter rroves constantly. OD-10331 . Valve 1CC40 Leaks. at flange connection Tightened bolts. OD-10202 #12 Boric Acid Seals leaking. Replaced rrechanical seals. Transfer Pump Replaced inboard and oui:board bearings. 

                                                  *-~--

OD-10099 *Valve 13MS168 Valve leaks. Fl "~ 'ted valve. Page 10 of 16 8-1-7 .Rl~-~

su~~*oF SAFETY RELA~ MAINTENANCE UN- NAME : _ _s_al_ern__#_l_ _ _ _ _ __ DEPARTMENT. Maintenance- DATE: _ _o_c_t_o_b_e_r_l_0..:..,_1_9_7_8_ _ REPORT MONTH September, 1~78 COMPLETED BY: L.K. Miller TELEPHONE: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. OD-10179 Valve 12CS1 Flange Leak Tightened bolts. i OD-10203* EL 100' Cont. High air leak rate. Repaired poor seal. J?ersonnel Air I.Dck. OD-10204 #15 Service Backwash pipe leaks. Tenporary pipe patch. Water Strainer. OD-10243 #16 Service Water Packing gland leaks. Adjusted packing gland. Strainer. OD-10250 Valve 2SW105 Packing leaks.

  • Replaced lubricator wi:th pipe
                                                               . ..                       *plug
  • OD-10321 #l4RHR Smrp Purrp Fails to start in auto *.
  • Cleared ground and cleaned wire terminals.

OD-10338 Valve 1CC196 Flqnge leaks. Tightened bolts. " MD-2680  :#13 *Reactor Modify #3.Seal Ring Clamp Completed DCR Coolant Pump I.A.W. DCR ED-0146-13 MD-2837 #1 Unit Cask Main heist nctor noisy. Replaced wonn gear shaft Handling crane aligned clutch assembly. MD-2895 #11 thru 15 Weld couplings to rrotor Completed. Fan Coil Units cooler nozzles. MD-2923 #11 Concentrate . Repair heat trace. Insulated exposed conductors. Transfer Purcp. MD-2996 #11 Carrp:>nent *4KV Motor Breaker will

  • Replaced* breaker control relays Cooling PUitp . not close.

OD-10368 #11 Fan Coil Motor Cooler leaks. 'Replaced Tl1otor Cooler. - Unit Pagell of 16 8-1-7.Rl

DUCl\Of;'I: NU~ - ---- '.)U-l /l _ _ _ SU?J..MAR.~* OF SAFETY RELAe MAINTENANCE UN- NAME : _ _ _s;;.,al......;.;;em~#;;.;;l;;,___ _ _ __ DATE:~_o_c_t_o_b_e_r__1_0 __ 1_9_7_8__~ DEPARTMENT Maintenance COMPLETED BY: L.K. Miller REPORT MONTH September, 1978 -------------------- TELEPHONE: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. OP-0346 #12 Reactor Modify #3 Seal Ring IAW Corrpleted DCR. Coolant Pump DCR ED-0146-12. OD-7992 #11 Steam Manway leaks. Repaired gasket surface. Generator OD-8529 Valve 11.NT22 Threaded connection Replaced gasket. leaking

  • OD-9488 COntairment ~pray Intennittent annunciator Replaced circuit board.

System alann. OD-10024 #11 Gas Stripper ICM discharge pressure. Disassembled and cleaned. Pump 

 . OD-10042          #16 Service Water      Packing gland leaks.                 Repacked.
~                    Pump.

OD-10123 IA Vital Blown fuse. Replaced circuit. board and Instrunent fuses. Inverter OD-10133 #26 Service Water 4Kv Breaker will not rack Ra~g m:>tor repaired.

  • Pump up~

OD-10141 #11 Service Water Flex Coupling leaks. Replaced flex coupling. Pump. OD-10146 #12 Service Water. Flex Coupling leaks. Replaced flex coupling. Pump OD-10147 #15 Service Water Packing gland leaks. Repacked. Strainer. OD-10158 #14 Fan Coil Unit Motor cooler leak. Replaced rrotor cooler. OD-10163 Valve llCSl Flange leak. Tightened bolts. Page 12 of 16 8-1-7 .Rl

SUMMAR.~l OF SAFETY RELAe MAINTENANCE UN-NAME:. DATE: Salem #1 O.ctober 10, 1978 DEPARTMENT Maintenance 

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

REPORT MONTH September, 1978 COMPLETED BY: L.K. Miller 

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

TELEPHONE: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. ** r--~~~~-t-~~--~~---r--~~..;..._~--~~~-t-~~---~---~~~~---~1 OD-10451 Valve 1CV6 Plug on Valve Body is Tightened bolts. leaking. OD-10449 llRID Bypass Flow orifice FE499A Tightened flange. Loop. flange leak. MD-2846 Valve . 13CV78 Bonnet leak. Terrporarily furmanited OD-9071 #11 Boric Replace rrechanical seal. Replaced seal. Acid Transfer PUIIp. Page 13 of 16 8-1-7.Rl

SALEM I OPERATING

SUMMARY

SEPTEMBER, 1978 9-1 The unit remained at full load for the day. thru 9-2 9-3 The unit was at full power until a vacuum leak required the load to be reduced at ~10%/hour to 94% load at 1105. The cause of the vacuum reduction was due to loss of seal water to #11 vacuum pump seals. The seal water was restored and the unit was increased to full load by 1254. The unit remained at full load for the remainder of the day. 9-4 The unit remained at full load for the day. thru 9-8 9-9 At 0035 a load decrease was initiated due to high differ-ential pressure across the condensate strainers. Load was decreased at ~5%/hour to 70%. The condensate strainers were cleaned and the load increased at ~5%/hour starting at 1155. The unit was at full load at 1825 and remained at full load for the remainder of the day. 9-10 The unit remained at full load for the day. thru 9-22 9-23 At 0045 load was decreased with rods to 76% in an attempt to prevent a reactor trip due to loss of #13 Condensate Pump. At 0046 a Reactor/Turbine trip occurred from 76%. The trip was due to the loss of #11 Feed Pump on low suction pressure resulting in #11 Steam Generator Lo water level with steam flow/feed flow mismatch. Page 14 of 16

9-25 The unit was taken critical at 0904. The delay in going critical was caused by faulty pressurizer spray valve operation, repair on #13 Condensate Pump and other main-tenance oriented repairs. The unit was synchronized at 1448. A load increase was initiated at 1500 and the unit reached 47% at 2400. 9-26 From 0001 to 1300 unit load was increased at 2-3% per hour to 83%. At 1325 unit load was decreased to 69% when #12 Condinsate Pump was taken out of service due to high temperature. A load decrease was initiated at 1506 to 10% per hour. and the unit reached 25% at 2010. Load was de-creased to allow taking #11 Condensate Pump out of service for maintenance. 9-27 Commenced load increase at 0005 at 1% per hour to a level of 'V32% at 0400. Load was held at 32% while maintenance on #11 and =IH2 Condensate Pump was performed. 9-28 Commenced load increase at 024*0 from 31% at 'V5% per hour to 55% at 0805. Load increase commenced at 1440 from 57% to 65% by 1610. Load remained at 65% for the remainder of the day while maintenance was being performed on #12 Condensate Pump. 9-29 Load remained at 'V65% until 2320 when a load increase was commenced at a rate of 'V5% per hour. 9-30 Load was increased at a rate of 'V5% per hour.Ae 0300 load was leveled off at 81.5%. Load increase recommenced at 0840 to 85% at 0955. At 1600 #11 Steam Generator Feed Pump. indicated bearing temperature problem. Load decrease was commenced at a rate of 5% per hour to a load of 50% at 2315. Page 15 of 16 

      °<J*

REFUELING INFORMAT. *_ DOCKET NO.: 50-272 UNIT.: Salem #1 DATE: October 10, 197 COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 MONTH: September, 1978

1. Refueling information. has changed from last month:

YES NO 

                                                                                       --- X
2. Scheduled date. of next refueling:. March 31, 1979
3. Scheduled date for restart: following. refueling: May 26, 1979
4. A.. Will. Technica1 Specification changes or other.* license amend.men ts be* required:?.

YEs** NO NOT DETERMINED- To~oATE September, 1978 B.. Has,_ the* reload* fuelc design. been reviewed. by the. Static~ Operating Review-. Conunittee? YEs* NO x If no, when is *it scheduled? _ _J_a_n_u_a_r_y,_.,_1_9_7_9_ _ _ _ _ _ _ _ __

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

February, 1979 if required. 6*. Important licensing co.nsiderations as.sociated with refueling: None - -7. Number of- Fuel Assemblies: A. In-Core 193 B. In* Spent Fuel Storage 0 8~ Present licensed spent fuel storage *capacity: 264 

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

Future spent *fuel. *storage capacity: 1, 1 7 O 

                                                                                       ------------------~
9. Da.te of last ref.ueling that can be . discharged to the spent fuel pool assuming the present licensed capacity: April, 1982.

Page 16 of 16

  • 8-l-7.R4}}
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