ML20238D506
| ML20238D506 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/31/1987 |
| From: | White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709110223 | |
| Download: ML20238D506 (12) | |
Text
- - -
FROM. SALEM p MIN OFFICE.
9,.2.1987 14 3 L3 p,
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l' MERAT1NG DMA FE'PCET Dochst No.50-272
[Aug st4 3 5-60'61_10
~
De,te
'M_ephone Completed by' Jell Wnite Extension j451
~~T Operating Status 1.
Unit Name Salem W.,.
1 Notes
-~
2.
Reporting Period
~3Ely 1987
~
- 3..
Licranse.d Thermal Power (MWt)
MT 4.;
Namcplate Rating (Gross MWe) 1170~
S.
Design Electra.ca) Rauing.(Met We)
Ef5 Maximum Dependable Ccpscity (Grocs. We)UT8 P 49 6.
Maximum Dependable Cr.pacity (!k.t MWe}
7.
8.
It Changes occur in Cap 6 city Ratings (Items 3 through 7) since Last Report, Give Reason _
N/A
+
wn
=
9.
Power Level to Which Restricted, if any '(Nat MWe)
NA
- 10. Reasons for' Restrictions, iir any
. NLA_,
_. = - _
~~
Thin Month Year to Date Cmoulative 5087
,88416 ___
f
- 11. Hours in Reporting Period 744 _ _ _ _
4902,T _,
56184.e
- 12. No. of Hrs. Reactor was Critical "T44 ~
~
~
- 13. Reactor Reserve Shut.down Hrs, 0
~
G~~
~
O' Q 14. Fcurs Generator On-Line 7I"d -
485% 2
~T01il. 8,_.
- 15. tin H Reserva shutdown liours o
0 0~ '
~~ ~
- 16. Gross Thermal Energy Generatc3 (MWH) 2383058.4 J5289370 167945416 1
- 17. Grosa Elec. Energy Generated (MWil) 166590 5084700 5570270 L
- 18. Net Elec. Energy Generated (WH) 733008 487707~4 53061842
~~
- 19. Unit Service Factor 100 95.4 66.4
~l6.4
- 20. Unit Availability Factor 100 9E I t
- 21. Unit Capacity Factor (using MDC Net) 89.1 BG.7 54.3
- 22. Uni.t capacity Factor 53.8_
(using DER Net) 8 6
_ 96 A __
8.4 14.7 O.79
- 23. Unit Forced Outage Eate date and duration of eachU
- 24. Shutdowns scheduled over r. ext 6 months (type s
{
_ Refueling 0u,tage - October 2 1987
,60 Days
,0 n
- 25. If shutdown at end of Report Period, Estimated Date of Startnp:
N/A
- 26. IiF,its in Test Status (Prior to Commercial Operation):
~
f F6 recast Achieved Initial Criticality 9/30/76 12/11/_76 Initial Electricity 11/1/76 jl225/76 commercial Operatien 12/20/75 6 /Tb7YY g
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50-272 N-Unit Name
'Nal~em # 1 Dat e August 10, 198_7 Completed by Pell White,
Telephone 609 935-6000 Extension 4451 Month August 1987 Day Average Daily Power Level Day Average Daily Powcr' Level
~
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FROM SALEM ADMIH OFFICE 9.
2.1987 t o gs p,
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MAJOR PLANT MODIFICATIONS DOCKUr NO.:
50-_72 2
REPORT MONTH July 1987 UMIT NAMES Salem 1 DATE ' August _12 T987 COMPLETED ' BY:L. Miller TELEPHONE:
609/339-4497
- DC R NO.
PRINCIPAL SY37Eh SUBJECT t
ISC-1200
oTduritylital scundry71 ace expanded metal over openings.for outside air intake ventilation systems.
This includeo ventilation.
as well as air conditioning.
1ET-1859 Imergency Dioncle Pre-Lube Pumps Replace this existing John Crane type 1 Mechanical Seal an anchor packing. type 8 Mechanical Seal to test.
Application of the seal to prevent lube oil leakage.
1EC-18~4A Service Water Revise the 8" SW emergency supply line to the Auxiliary Feedwater System from No. 12 SW nuclear header; Revise the g,j 4" SW supply line to the room and oil coolers from No. 12 SW nuclear header; Line or replace the stainless steal SW supply and return piping to No. 12 Component Cooling Noat Exchanger Add break flangen in the SW supply and return piping to No. 21 CCI1X.
I l
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DCR - Design Change Pequest
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, MAJOR.?LANT MODIFICATIONS DOCKET HO.
50-272
-REPORT. MONTH July 19_81 UNIT NEME:
Salem 1-a DATE:
August 12 1987 fl CCMPLETED BY lZ Miller-TELEPHONE; j09/339-4497
- DCR-SAFETY _ EVALUATION 10 CFR 50.59
~f l
1EC=1874A.
This design change enhanced the caferguards emergen6y controller test mode. 'The materials.
linstalled meet the design requirement qualification (Seismic. Class I).
No. other design criteria were affected by this change.
This modification did not affect any plant' process or-l discharge.
No unreviewed safety or enviremental
- i questions are involved.
15C-1200 This design change provided security barricts over the auxiliary building venti 11ation intake and exhaust ducts.
Implementation'did not affect the safe shu,down of the reactor.
This modification does not alter any plant process or discharge nor does it change the environmental impact of the plant.
No unreviewed safety on environmental lg,y.
questions are involved, involved.
1ET-1859 The implementation of this. design change did not affect any existing safety analynis or create any-new hazards.
The basis of.the technical specifications. remained unchanged..This change did not alter any plant process or discharge or:
affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
4
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BALEM GENERATING STATIDN1.
L (: 1 NONTHLY OPERATING
SUMMARY
- UNIT N0; I t
. JULY:1937' t,
o m
(# '
rne. unit' began the period oper attwy at enownLI.11y full pvww and continued to operate at ths, level, with the exception of a series of" minor load' reductions, for the entire pdrina, Load reductions were required dus to electrical. storm activity is. the vicinity; of the Salem-Dean's.500KV Transmission.Line, repet;ttive jamming: of the new :
stainless ~ steel 11B Circulating Water 'scre.st, loss of the New Freedom-lightning ; strike oc ' t.he 5021 Salem-Dean's i
500-4 transformer, and a line.
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REFUELIEC INFORMATION DOCKET tio. :
50-272
',,C OMPLETED DY.
L.K.
Miller UNIT NANE:
Salem 1-DATE: ' August 12, 1987 TELEPHONE:
509/935-6000 EXTENSIO*4 4497
~~
Month July 1987', _
l '.
Refueling information bee changed from Last month:
YES NO X
2.
Scheduled date for next refueling:
October _3, 1987 3.
Scheduled date for rest. art following refueling: December 4, 1987
-f.
A)
Will Technical Specification changes or other license amendments be-required?
I YES.
N O __ __
i NOT btititHINED TO DATE 7
B)
Has the reload fuel design been ~ reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it schedul.ed?
September 1_987 __
5.
scheduled date(s) for submitting propossa licensing actions
/
Septiurrber 1987 if required s
6.
Important licensing considerations associated with refueling a
NONE o
7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage
_380 8.
Present licensed spent fuel storege capacity:
1170 l
Future spent fuel storage capacity:
1170 s,
f' Date of last refueling that can be discharged 9.
.o.
to spent fuci pool assuning the present licensed capacity:
September 2001 4
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FROM SRLEM e
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1 t r.,, c.... i b-Q ham Generating Station Augurt 12, 1987 s
i U.S. Nuclear Regulatory Comniasien Document Control Desk i
Washington, DC 20555
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Dear Sir t CerO I'
MONTHLY OPERATING REPORT SALEM NO. l' 7
DOCKET No. 50-27 2 l
In compli%nce with Section 6.9.1.6, Esporting Requirements for the Salem Tepnnical Specifications, the original copy of the monthly operatingireports for the month of July 1987 are being sent to you.
Average Daily Unit Power Level Operating Dettt. Report Unit Shutdowns and' Power Reductions Safety Related Maintenance Q
Mejor Plant Modification Ope rating 5ttrwary Refur. ling Information Sincerely yours,
4 d%
J./ 4. Zupko[Jr.
General Meneger - Salem Operations Rii t al cc1 N.r. William T 4 Russell
~
Regional Administrator USNRC Region I 631 Park Avenue King of Drussia, PA 19406 Enclosurea 8-1-7.R4 Q
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