ML20238C845
| ML20238C845 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1987 |
| From: | Miller L, White P, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8709100407 | |
| Download: ML20238C845 (14) | |
Text
.
FROM 5ALEM ADMIN OFFICE 9.
2.1987 14: 05 P.
4 OPERAT.ING DATA REPORT Docket No.50-272 Date July ~10,1TIF F ToLephone DT5-600ff~
Completed by Poll White Extension 4451
~
Operating Status 1.
Unit Name Sa'.em No. 1 Notes 2.
Reporting Period
'TuTe 19 8 7 3.
Licensed Thermal Power (MWt)
JTfI 4
Nameplate Rating (Gross MWe)
TT75 S.
Design Electrical Rating (Net MWe)
ITTI G.
Maximum Dependable Capacity (Gross MWe) TIT!I 7.
Maximum Dependable Capacity (Net MWe) TY6E 8.
If Chenges occur in Capacity Ratings (TUiiEs 3 through 7) since Last Report, Give Reason N/A 9.
Power Level to Which Restricted, if any (Net MWe)
NA
- 10. Ronsons for Restrictions, if any N/A
_ - = -
This Month Year to Date Cumulative
- 11. Hours in Reporting Period 720 4343 87600
- 12. No. of Mrs. Reactor Was Critical 6 BC" 4158.2
~15 4 4 0. 51 -
- 13. Reactor Reserve Shutdown Hrg4 0
0 0
~~~~
- 14. Hours Genetator On-Line 6 61. 5 ~
4109.2
'i 3 5 3 7. 'll ~~
~
~
- 15. Unit Rentve Shutdown HourE
~
~~~~
O O
0
- 10. Gross Thermal Energy Generated
~
(MWH) 2192781.6 12906311.6 165562357.6
- 17. Gross Elec. Energy Generated
~~
~~
(MWH) 729220 4318110 55016110
- 18. Met Elec. Energy Generated (MWH) 696865 4144066~
's232883T"'
- 39. Unit Service rhetor 94.i~ ~
94.6 61.1 ~
- 20. Unit Availability Factor 947~~~~
94.6
- 61. T-~~
- 21. Unit Capacity Factor (using MDC Net) 87,5 86.3 54._0
- 22. Unit Capacity Factor (using DER Net) 86,5.J _
53.6 85.6
- 23. Unit Forced Outage Rate 4
5.4 25.1
- 24. shutdowns scheduled over next 6 rienths (type, date and duration of each)
_Refuelin_g Outage - October 2, 1987 -
E0 3 y L,_____ _ _,,,,
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A
- 26. Unit? ~in Test Status lPrior to'C'ommerca.a1 Operatioidi Foreratt Achieved Initial C::iticality 7 737[7I6 12/11/75 Initial Electricity I'l/1/76 12/25/76 Commercial Operation 17/20/75 l6/30/77 8-1-7.R2
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FFOM 5ALEN ADMIN OprICE' 9.
2.1987 14se:5 P,
3 AVERAGE DA7LY UN.fT POWER LWEL Docket Net.
'50-272 s
Unit Namt<
_ Sa le:n 'T T Date
__ JULY Tf,T9 8 7 Completed by Pell White Telephone 609-935-cT6F Extensicn T451
~ '"
Month June:_ _ 1987-Day Average Daily Power Level Day Average Daily Power.Lovel (l@e-NET)
(MWu-NET) 1 988 17 1097 2
413 IB J104 3
0 19 iO97 4
S18 20
.- 7 3
- 0. -
5 1097 21 885 6
1097,_
22 787 7
104S 22
.E S 2 0
1106 24 1069 9
_975 2S 9 e.6.~_
10 1071 26 t091 11 1131 27 1000 12
_ 1103 28 10C9 13 875 29 1078 14 1095 30 1073 15 1987 31 16 1107 P.
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609 935 2058 S
FROM S A L E.1 ADMIN OFFICE 9.
2.1987 14809 P.11 MAJOR PLANT MODIFICATIONS DCCKET NO.:
50-272 REPORT MONTH JUNE 1987 UNIT NAME:
salem 1 DATE:
July 10, 1987 COMPLETED BY:
L. Miller TELEPHCNE:
609/339-4497 "DCR NO.
PRINCIPAL 8METEM SUBJECT isc-1312A Containment Instal.1 an a.larm system to Air Lock warn personnel of inadvertent airlock pressurization in the j
event meal leak into the
[
airlock.
ISC-1312B Containment Install caps and valving Personnel Hatch at personnel hatch -
El. 100 f. 130.
i l
l 1
l DCR - Design Change Request l
F R O.M SALEN ADMIN OFFICE 9.
2.1987 14: 03 P.12 i
MAJOR PLANT MODIFICATIONS DOCKET NO :
30-272 REPORT MONTIl JUNE 1987 UNIT NAME:
S a l e m l_____
DATE:
July 10, 1987 COMPLETED BY:
L.
Miller TELEPHONE:
_609/339-4497
- DCR SAFETY EVALUATION 10 CFR 50.59 1sc-1312A The intended function of the system remains the same.
This design change involved the routing of 3
cables for an alarm system to warn personnel of j
inadvertent airlock pressurization, This did not 1
affect the function of the containment airlock system or any other safety related system.
This modification did not alter any plant process or discharge or affect the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
isc-1312B This changG modifed the design of the air test line for the 100'and 130' elevation airlocks.
This design modification removed all non-qualified gages which were part of the containment bocndary and added either Nuclear class II manually operated, normally closed contianment isolation valves or capped off the gage connections.
The gages which were removed had to be removed since they were not qualified to the accident conditions and qualified gages were not available.
The gages represented a potential for leakage out of the contianment post-LOCA.
The revised design still allows the plant operators to perform all tests for airlock integrity required by the Technical specifications.
The new design meets General Design Criteria 57 for containment penetration, i
The door son 1 constitutes the "close system" inside containment and a normally closed valve (1CA1714 or 1CA1715) constitutes the outboard isciation barrier.
The design also complies with 10CFR50 Appendix J requirements in that it allows for leak tenting of the isolation barrier.
The new line design reets all applicable containment isolation requirements and still meets all its functional requirements.
This modification does not alter any plant process or discharge nor does it change the environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
DCR - Design Change Request
MON SALEM ADMIN OFFICE 9.
2.1987 1481e P.13 SALEM CENERATING STATION MONTHLY OPEPATING
SUMMARY
- UNIT NO. 1 JUNE 1987 The unit began the period cperating at one hundred percent (100%)
power and continued at that level until June 2,1987, when the Trip-A-Unit protection tripped the Unit during an electrical storm.
Lightning had struck the 5021 transmission line and caused the protective relays to operate.
The Trip-A-Unit function had not been disabled because the storm severity was two levels below the established criteria.
On June 4, 1987, folicwing synchronization, power was held at a reduced level due to electrical storm activity in the area.
The Unit returned to one hundred percent (100%) power on June 5, 1987, when power was reduced due to electrical storm activity in the area.
The Unit returned to one hundred percent (100%) power on June 10, 1987, and continued to operate at that level until June 13, 1987, when power was reduced due to electrical storm activity in the area.
On June 14, 1907, the Unit Aaturned to one hundred percent (100%) power and continued to operate at that level until June 20, 1987.
On June 20, 1987, power was reduced to eighty percent 80%) to swap the Trip-A-Unit Scheme control from Unit I to Unit 2.
The Unit continued to operate at that level until June 22, 1987, when power was further reduced to sixty percent (60%) due to electrical storms in the area.
The Unit returned to one hundred percent (100%) power on June 23, 1987, and continued to operate at that level until June 25, 1987, when a brief load reduction was performed.
The Unit returned to one hundred percent (100%) power Inter the same day, and continued to operate at that level for the remainder of the period.
FROM SALEM ADMIN OFFICE 9.
2,1987 14: 11 P.14 REFUELING INFORMATION DOCKET 90.s 50-272 COMPLETED BY:
L.K. Miller UNIT NAME:
Salem 1
'~
DATE:
July 10, 1987 TELEPHONE:
609/935-6000 EXTENSION:
1497 Month June 1987 1.
Refueling information has changed from last month:
YES _
NO,
X 2.
Scheduled date for next refueling:
October 3, 1987 3.
Scheduled date for restart following refueling: December 17, 1987
{
4.
A)
Will Technical Specification changes or other license amendments he required?
YES NO NOT DETERMINED TO 6A'IE X
B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it 33hTduled?
September 1987 S.
Scheduled date (s) for submitting proposed licensing action:
Septe3ber 1987 if required 6.
Important licensing considerations associated with refueling:
NONE 7.
Number of Fuel Assemblies:
A)
Incore 193 B)
In Spent Fuel Storage 380 8.
Present licensed spent fuel storage capacity:
1170 Puture spent fuel storage capacity:
1170
- 9.
Date of last refueling thn: can be discharged to spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7,R4 y
e
FROM SALEM ADMIH OFFICE 9.
2.1997 14804 P.
2 Of
/&
C O PSEG 7((J Put>lic Smuke Electric and Gas Company P.O. Bc x E Hancock s Bridge, NeuJersey 00030 Salem Generating Station July 10, 1987 Director, of fice of Manageraent U.S. Nuclear Regulatory Conunlesion Document Control Desk Washington, DC 20555 DESIGNA ORIGU Certified D MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the salem Technical Specifications, the original copy of the monthly operating reports for the month of June 1987 are being sent to you.
Average Daily Unit Pcwer Level Operating Data Report Unit Shutdcwns and Power Reductions Safety Related Maintenance Major Plant Modification Operating Summary Refueling Information Sincerely yours, (n e J.
4.
k, Jr.
G era Manager - Salem Operationsi RH:sl ec Mr. William T.
Eusse11 Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Enclosures B-1-7.R4
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