ML20236B422

Monthly Operating Repts for Sept 1987

ML20236B422
Person / Time
Site:	Peach Bottom
Issue date:	09/30/1987
From:	Alden W, Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8710260169
Download: ML20236B422 (14)

Text

{{#Wiki_filter:- _ _ NRC Monthly Operations Sumary Peach Bottom Atomic Power Station 1 -September, 1987 UNIT 2 The unit remained shutdown throughout the report period. The outage was reclassified from a Forced Regulatory Outage to a Refueling / Maintenance Outage as of September 28, 1987, to indicate the resumption of refueling activities i that were postponed to accomodate activities associated with the Commitment To Excellence Program. All outage work, prior to. initial rod. withdrawal, is expected to be completed by November 24, 1987. On September 4, the de-energization of the 'A' Residual Heat Removal logic resulted in_.a Shutdown Cooling isolation during a fuse panel investigation. A loose wire and fuse connection-were-the root cause of the event. De- ) energization of the fuse caused a protective relay trip, resulting in the Soutdown Cooling isolation. Subsequently, the loose connection was tightened and Shutdown Cooling was promptly restored. Later on September 4, while performing'a surveillance test, a resistor in the High Pressure Coolant Injection (HPCI) System power supply was found to be defective, thus rendering HPCI inoperable. Investigations into the resistor failure were not conclusive in determining the cause. However, the resistor was replaced and an engineering evaluation will be performed to determine possible alternatives for providing a more reliable power supply. On September 16, the Primary Containment Isolation System initiated the outboard isolation of the Reactor Building Ventilation System (Secondary Containment) and the automatic actuation of the Standby Gas Treatment System while clearing a c blocking permit following modification work. The isolations were reset and the blocking permit was removed. The same day, a Primary Containment Group II inboard isolation occurred while performing support work for a lighting system modification. A temporary lighting feed was supplied from the Group II inboard din, inution panel (20Y33) at the time of the event. It is suspected that a breaker which feeds the y distribution panel was opened and then reclosed, causing a momentary de-energization of the panel and initiating the isolations including Shutdown Cooling; however, investigations have not conclusively revealed the cause of the event. The isolations were reset and Shutdown Cooling was restored within ten minutes. Unit 3 The unit remained shutdown throughout the report period in compliance with the NRC March 31, 1987 Order. Preparations for the refueling and pipe replacement outage, scheduled to begin on October 1, 1987 continued throughout the month. l; 8710260169 070930 PDR ADOCK 05000277 (/ R PDR Il a

Docket No. 50-277 Attachment to Monthly Operating Report for September,1987 UNIT 2 REFUELING INFORMATION 1. Name of facility: Peach Bottom Unit 2 2. Scheduled date for next refueling shutdown: Reload 7 in progress 3. Scheduled date for restart following refueling: Indetenninate due to Shutdown Order 4. Will refueling or resumption of operation thereaf ter require-a -technical specification change or other license amendment? Yes If answer is yes, what, in general, will these be? Technical Specifications to accommodate reload fuel. Modifications to reactor core operating limits. (Reload 7 amendment issued September -11,1987) 5. Scheduled date(s) for submitting proposed licensing action and supporting information: Reload 8 license amendment to be submitted January 1989. I i 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating i procedures: None expected. 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool: (a) Core - 764 Fuel Assemblies, Core Offloaded During Outage (b) Fuel Pool - 1462 Fuel Assemblies, 58 Fuel Rods 8. The present licensed spent fuel pool storage capacity and the size of any l increase in licensed storage capacity that has been requested or is l { planned, in number of fuel assemblies: The spent fuel pool storage capacity has been relicensed for 3819 fuel l l assemblics. l l l

Docket No. 50-277 Attachment to l I Monthly Operating Report for September,1987 Page 2 -f l UNIT 2 REFUFLING INFORMATION (Continued) l 9. The projected date of the last refueling that'can be discharged to the-spent fuei pool -assuming the.present. capacity.. subsequent, to the. completion of the new fuel racks installation: j March,1998 (March 1995, with reserve full core discharge) ] J

Docket No. 50-278 Attachment to Monthly Operating Report for September, 1987 UNIT 3 REFUELING INFORMATION 1. Name of facility: l Peach Bottom Unit 3 2. Scheduled date for next refueling shutdown: October,1987(MajorPipeReplacementOutage) 3. Scheduled date for restart following refueling: July 9, 1988 4. Will refueling or resumption of = operation thereafter require a technical specification change or other license amendment? Yes. If answer is yes, what, in general, will these be? Technical Specifications to accommodate reload fuel. Modifications to reactor core operating limits. 5. Scheduled date(s) for submitting proposed licensing action and supporting information: Reload 7 License Amendment to be submitted March 11, 1988 6. Important licensing considerations associated with refueling, e.g., new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedJres: None expected. 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool: (a) Core-764fuelAssemblies (b) Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods

Docket No. 50-278 Attachment to Monthly Operating Report for September, 1987. Page 2 UNIT 3 REFUELING INFORMATION (Continued) 1 I 8. The present licensed spent fuel-pool' storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of-fuel assemblies: l The spent fuel pool storage capacity has been relicensed for 3819 fuel I assemblies. -This modification began on February 20, 1987. The . completion date for this modification has been rescheduled for February,1989-to accomodate the Unit 3 pipe replacement outage. 4 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of the-new fuel racks installation: March. 1993 (reserve full core discharge cannot be accommodated after the restart following the completion of the October, 1987 refueling outage until the completion of the new fuel racks)

10. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, subsequent to the completion of the new fuel racks installation:

March 1999 (March,1996, with reserve f ull core discharge) l 1 1 l I I i

i g .m- ' AVERAGE DAILY UNIT P0HER LEVEL DOCKET No. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE OCTOBER 15, 1987 COMPANY PHILADELPHIA ELECTRIC CN1PANY L. L. MIDDLETON 1 TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE (215) 841-6374 j HONTH SEPTEMBER 1987 DAY AVERAGE DAILY PONER LEVEL DAY : AVERAGE DAILY P0HER LEVEL l ( N4E-NET ) (HHE-NET) l i

1 0

17 0 i 2 0 '18 0 3 0 19 0 0 0 20 0 5-0 21 0 6 0 22 0 7 0 23 0 Q 0. 24 0 -9 0 25 0 10 0 26 0 I 11 0 27 0 4 ~ l-12 - 0 28 0 13-0 29. 0 i !l. 14 0 30 0 ) 15 0 L i 16 0 l l' ) l l

..s ' AVERAGE DAILY UNIT'P0HER LEVEL' DOCKET NO. 50 - 278 UNIT PEACH BOTTOH UNIT 3 I DATE OCTOBER 15, 1987 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL ASSISTANT. l LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT ^ ! (,, TELEPHONE (2151 041:6374 I HONTH SEPTEMBER 1987. D AY.' AVERAGE DAILY P0HER LEVEL ' DAY AVERAGE DAILY P0HER LEVEL-( ME-NET) ( ME-NET) 1 0 17 0 i 2 0 18 0 3' O. 19 0 4 0. 20 0 I 5 0 21 0 i 6 0 22 0 ) 7 0 23 0 8' O 24 0 l 9 0 25 0 f e e 10 0 26 0 l 11 0 27 0 l 12 0 28 0 13 0 29 0 14 0 30 D 15 0 16 0 V.

h..- 3 l: DPERATING DATA REPORT. . DOCKET NO. 50 - 277 i i ~ DATE OCTOBER 15,'1987 l l COMPLETED BY PHILADELPHIA ELECTRIC COMPANY j L. L. HIDDLETON. l TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT ' TELEPHONE (215) 641-6374 OPERATING STATUS' ......................==_------.........

1. UNIT NAME: PEACH BOTT0H UNIT 2'

-l NOTESt' UNIT 2 REMAINED SHUTDOM l l l . 2. REPORTING PERIODI SEPTEMBER, 1987 l .IN ACCORDANCE HITH THE-l l

3. LICENGED THERHAL P0HER(HNT)*

3293 .I HARCH 31, 1987 NUCLEAR, i 1 l. l.

4. NAMEPLATE RATING (GROSS PME le

'1152 l REGULA*iORY comISSION ORDER, l l l

5. DESIGN ELECTRICAL RATING (NET HHE)#

1065 l UNTIL SEPTEMBER 28 HHEN l l~ - l

6. KAXIMUM DEPENDABLE CAPACITY (GROSS HHE)8 -1098 l-REFUELING ACTIVITIES HERE

.l l l

7. HAXIHUM DEPENDABLE CAPACITY (NET HHE ):

1051 l RESUHED. l 8.' IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUteER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI

9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY (NET HHE le

10. REASONS FOR RESTRICTIONS, IF ANYt.

THIS HONTH YR-TO-DATE CUHULATIVE

11. HOURS IN REPORTING PERIOD 720 6,551 116,063

12. NUMBER OF HOURS REACTOR HAS CRITICAL 0

1,729.8 74,196.8

13. REACTOR RESERVE SHUTDOHN HOURS 0.0 0.0 0.0

14. HOURS GENERATOR OH-LINE 0.0 1,724.0 71,866.8 15.' UNIT RESERVE SHUTDOHN HOURS 0.0 0.0 0.0 16.' CROSS THERMAL ENERGY GENERATED (HHH )

0 4,979,376 212,810,745

17. GR03S ELECTRICAL. ENERGY GENERATED (HHH1 0

1,648,230 70,019,230 1j.

18. NET ELECTRICAL ENERGY GENERATED (HHH)

-5,457 1.565,378 67,054,238 PAGE 1 0F 2 i

l. I: 4 [. [ OPERATING DATA REPORT (CONTINUED) DOCKET NO. 50 - 277 1' I [ '. k DATE DCTOBER 15, 1987 THIS HONTH 'YR-TO-DATE CUHULATIVE

19. UNIT SERVICE FACTOR 0.0 26.3 61.9 20.' UNIT AVAILABILITY FACT 0k.

0.0 26.5 .61.9

21. UNIT CAPACITY FACTOR (USING HDC NET) 0.0 22.7 55.0

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 22.4 54.2

23. UNIT' FORCED DUTAGE RATE 100.0 42.9 14.6

- 24.' SHUTDOHNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH): REFUELING OUTA0E

25. IF SHUTDOHN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP8 l

' 26. UNITS IN TEST STATUS (PRIOR TO COHHERCIAL OPERATION) FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73-l INITIAL ELECTRICITY 02/18/74 i CONMERCIAL OPERATION 07/05/74 PAGE 2 0F 2

1. - NEGATIVE VALUE HEPORTED FOR CONSISTENCY HITH FEDERAL ENERGY REGULATORY COMMISSION REPORTS.

3

L. .) s ','~ ,J-5, t JDPERATING. DATA REPORT. 1-i -DOCKET No. 50 - 278 l \\ DATE OCT08ER 15, 1987-w COMPLETED BY PHILADELPHIA ELECTRIC COMPANY j n .L. L. MIDDLETON TECHNICAL ASSISTANr LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT- . TELEPHONE (215) 841-6374 OPERATING STATUS s................

1. UNI'T NAMES PEACH BOTTOM UNIT 3 l NOTES UNIT 3 REMAINED SHUTD06@(

l g-l. 4C.. REPORTING PERIODI SEPTEMBER, 1987 l IN ACCORDANCE HITH THE l l l J3. LICENSED THERHAL P0HERIMHT): 3293 l HARCH 31, 1987 NUCLEAR l- -l l ~ 42 NAMEPLATE RATING (GROSS PME 18 1152 l REGULATORY C0ttlISSION ORDER. 'l l l

5. DESIGN ELECTRICAL RATING (NET MHE ):

1065 l l ~ l l < 6. HAXIMUN DEPENDABLE CAPACITY (GROSS HHEll 1098 l l ( l l

7. HAXIMUN DEPENDA0LE CAPACITY (HET MNE):

1035 1 l

8. IF CHANCES OCCUk IN CAPACITY RATINGS (ITEMS NUteER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI

9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY (NET MNE)*

10. REASONS FOR RESTRICTIONS, IF ANY THIS MONTH YR-TO-DATE-CUMULATIVE

11. HOURS IN REPORTING PERIOD 720 6,551 111,959

12. NUMBER OF HOURS FiaCTOR HAS CRITICAL 0

1,824.9 76,357.4 . 13. REACTOR RESERVE SHUTDOHN HOURS. 0.0 0.0 0.0 14.' HOURS GENERATOR ON-LINE 0.0 1,659.6 73.929.3

15. UNIT RESERVE SHUTDOHN HOURS 0.0 0.0 0.0

16. CROSS THERMAL ENERGY GENERATED IMHH1' O

4,759,248 215,278,901 I

17. GROSS ELECTRICAL ENERGY GENERATED (MHH) 0 1,555,560 70,611,432

- 18. NET ELECTRICAL ENERGY GENERATED (HHH) -5,457 1,473,184 67,715.277 PAGE 1 0F 2

^ \\;. ,J.- Ip OPERATING DATA REPORT (CONTINUED) DOCKET No. 50 - 2F8' L t-DATE OCTOBER 15, 1987' THIS HONTH .YR-TO-DATE CUHULATIVE l r

19. UNIT SERVICE FACTOR 0.0

25..t 66.0 c20. UNIT AVAILABILITY FACTOR-0.0 25.3 66.0

21. UNIT CAPACITY FACTOR (USING HDC NET) 0.0 21.7 58.4'

....- --- = 1

22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 21.1 56.8

==-. 23 1 UNIT FORCED OUTAGE RATE 100.0 74.7 13.3 q . 24. SHUTDO M SCHEDULED OVER NEXT 6 HONTHS (TYPE. DATE, AND DURATION OF EACH) . i1 INDETERMINATE UNTIL-NRC ORDER IS SATISFIED.

25. IF SHUTDOMN AT END OF REPORT PERIODS ESTIMATED DATE OF STARTUPI l

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)I FORECAST ACHIEVED INITIAL CRITICALITY -

06/07/74 i INITIAL ELECTRICITY 09/01/74 COHHERCIAL OPERATION 12/23/74 1 1 PAGE 2 OF 2 l l l

1 I" v -1 l' i: ~U i .? UNIT SH'JTD0&NS AND P0HER REDUCTIONS DOCKET NO. 50 - 277 l UNIT NAME PEACH BOTT0H UNIT 2- -{ y -DATE OCTOBER 15, 1987 1 REPORT HONTH SEPTEMBER, 1987. COMPLETED BY PHILADELPHIA ELECTRIC COMPANY' L .L. L. MIDDLETON TECHNICAL ASSISTANT., LICENSING SECTION 'l NUCLEAR SUPPORT DEPARTHENT TELEPHONE ( 215) 841-6374 6............................................................................................................................ i l; I l l l HETHOD OF l LICENSEE lSYSTEMICOMPONENTl CAUSE AND CORRECTIVE ^l a l l' ITYPElDURATIONlREASONISHUTTING DOHNj ' ' EVENT l CODE I CODE l ACTION TO ..I3-{DATE 1 (1)l (HOURS)I (2) l REACTOR ( 3 ) l REPORT # 1 (4) 1 (5) l PREVENT RECURRENCE a.................. _=...............__==__

l l

l 1-I l' l 1 1 6 1 G70901 1 F l 648.0. l D I -1 1 N/A 1 ZZ l 777777 l SHUTDOHN OF UNIT DN THE ORDER OF THE NRC. I~ ~l' I I I I I I I 7 l 8F0D38 l S-l'072.0 'l 'C l 1 l N/A. I RC l FUELXX l RESUHPTION OF REFUEL ACTIVITY .l. I I ----- 1 I I I I i l 'I I l 720.0 'l' l l l l I i I 1 (1) (2) (3) (4) k - F0ZCED REASON METHOD EXHIBIT G ~ INSTRUCTIONS 3 - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - HANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER) j 0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161) l E - OPERATOR TRAINING + LICENSE EXAMINATION I LF - ADMINISTRATIVE (5) G - OPERATIONAL ERROR (EXPLAIN) H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE 3 l l 'h 1 1 I i

$ I 1 i l I UNIT SHUTDOPNS AND P0HER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 J 1 1 "DATE' OCTOBER'15, 1987E ) l REPORT HONTH SEPikHBER, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTIDH NUCLEAR SUPPORT DEPARTHENT. TELEPHONE (215) B41-6374 e..'.................. l l l l l NETHOD OF l LICENSEE ISYSTEMICOMPONENTl CAUSE AND CORRECTIVE l' - l TYPE l DURATION I RE ASON I SHUTTI NG DONN I ' EVENT l CODE I ' CODE I ACTION TO. j %3. l ?? DATE - l (1)l ( HOURS )l (2) l REACTOR (3) 1-REPORT # l 14) l (5) l PREVENT RECURRENCE m....................................................................................=----- =................................ I: l-I I I I I I I '6;l 870901 l F.l 720.0- l D 1 1 1 N/A l ZZ l 777777 i SHUTDONN OF UNIT ON THE ORDER OF THE NRC. I I I ----- 1 I I I I I i 1 l -. 720. 0 l I l l l I (1) (2) (3) (4) 7 - FORCEO REASON HETHOD EXHIBIT G - INSTRUCTIONS 3. SCHEDULED. A - EQUIPHENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER) D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE INUREG-0161) E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5) j ~ 0 - OPERATIONAL ERROR (EXPLAIN) H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE j l l l l I I l

n USHRC-DS' P, PHILADELPHIA ELECTRIC COMPANY l l 2301 MARKET STREET g g g:#' % 5.8p;n - P,0. BOX 8699 PHILADELPHIA A, PA.19101 121si e414ooo i October 20, 1987 l l Docket Nos. 50-277 l 50-278 Director Office of Inspection & Enforcement l US Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

SUBJECT:

Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen: Attached are twelve copies of the monthly operating report for Peach I Bottom Units 2 and 3 for the month of September 1987, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4. We regret the late submittal of this report. Very truly yours, I W. M. Alden Engineer-In-Charge Licensing Section Nuclear Support Department LLM:mlh Attachment cc: W. T. Russell, Administrator, Region I USNRC T. P. Johnson, PBAPS Resident Inspector S. P. Mangi Dept. of Envir. Resources P. A. Ross, NRC (2 copies) R. E. Martin, NRC Project Manager Thomas Hagette, Maryland Power Plant Siting INP0 Records Center ,}}