ML18100A474
| ML18100A474 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/30/1993 |
| From: | Shedlock M, Vondra C Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9307190096 | |
| Download: ML18100A474 (11) | |
Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station July 14, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
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 1993 are being sent to you.
RH:pc Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance 10CFR50.59 Evaluations Operating Summary Refueling Information Si~ y yours,.
g;f{iL
-General Manager -
Salem Operations cc:
Mr. Thomas T. Martin Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19046 Enclosures 8-1-7.R4 rJ ~~~~~ ~
1eople
- ---9307190696 PDR ADOCK R
930630 05000272 PDR
~ERAGE DAILY UNIT POWER L~L Docket No.:
50-272 Unit Name:
Salem #1 Date:
7/10/93 Completed by:
Mark Shedlock Telephone:
339-2122 Month June 1993 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 1060 17 0
2 1104 18 0
3 1065 19 0
4 1128 20 279 5
1062 21 800 6
1102 22 1082 7
1104 23 1100 8
793 24 1086 9
0 25 1085 10 0
26 1042 11 0
27 1073 12 0
28 1100 13 0
29 1093 14 0
30 1062 15 0
31 16 0
P. 8.1-7 Rl
OPERATING DATA REPORT Docket No:
Date:
Completed by:
Mark Shedlock Telephone:
Operating Status
- 1.
Unit Name Salem No. 1 Notes
- 2.
Reporting Period June 1993
- 3.
Licensed Thermal Power (MWt) 3411
- 4.
Nameplate Rating (Gross MWe) 1170
- 5.
Design Electrical Rating (Net MWe) 1115
- 6.
Maximum Dependable Capacity(Gross MWe) 1149
- 7.
Maximum Dependable Capacity (Net MWe) 1106
- 8.
If Changes Occur in Capacity Ratings (items 3 through 7)
Report, Give Reason NA 2
- 9.
Power Level to Which Restricted, if any (Net MWe)
- 10. Reasons for Restrictions, if any
- 12. Hours in Reporting Period
- 12. No. of Hrs. Rx. was Critical
- 13. Reactor Reserve Shutdown Hrs.
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Elec. Energy Generated (MWH)
- 18. Net Elec. Energy Gen.
(MWH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (using MDC Net)
- 22. Unit Capacity Factor (using DER Net)
- 23. Unit Forced Outage Rate NA This Month Year to Date 720 4343 460.76 3827.67 0
0 446.85 3728.20 0
0 1457001.6 11840913.6 482120 3959730 453516 3771903 62.1 85.8 62.1 85.8 57.0 78.5 56.5 77.9 37.9 14.2 50-272 07/10/93 339-2122 since Last N/A Cumulative 140280 93009.65 0
89868.61 0
284039522 94332720 89843562 64.1 64.1 57.9 57.4 21.2
- 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
Refueling, 10-02-93 approximately 72 days.
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
NA 8-l-7.R2
NO.
DATE 0086 6/01/93 F
0087 6/01/93 F
0088 6/05/93 F
0089 6/06/93 F
0090 6/06/93 F
0091 6/08/93 F
0092 6/20/93 F
0093 6/26/93 F
0094 6/30/93 F
1 2
F:
Forced S:
Scheduled DURATION TYPE1 (HOURS)
REASON2 4.33 B
18.42 B
4.60 B
3.80 B
2.20 B
272.70 A
.45 B
20.37 B
8.82 B
Reason A-Equipment Failure (explain)
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction UNIT SHUTDOYN AND POYER REDUCTIONS 5
5 5
5 5
3 4
5 5
REPORT MONTH JUNE 1993 METHOD OF SHUTTING DOYN REACTOR LICENSE EVENT REPORT #
HF HF HF HF HF HF CJ IF HF 3
Method:
1-Manual 2-Manual Scram SYSTEM CODE 4
E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
H-Other (Explain)
COMPONENT CODE5 PUMPXX PUMP XX PUMP XX PUMP XX PUMP XX PUMP XX INSTRU INSTRU PUMPXX 4
DOCKET NO.
UNIT NAME DATE COMPLETED BY TELEPHONE 50-272 Salem #1 07/10/93 Mark Shedlc;ck 339-2122 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE CONDENSER TUBE PROBLEMS CONDENSER TUBE PROBLEMS CONDENSR TUBE & YATER BOX CLEANING CONDENSER TUBE & YATER BOX CLEANING CONDENSER TUBE & YATER BOX CLEANING CIRCULATING YATER PROBLEMS OTHER REACTOR COOLANT SYS INSTR. PROBLEMS PRESSURIZER PRESS. INSTRU. & CONTROLS CIRCULATING YATER PUMPS 5
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File Exhibit 1 - Same Source (NUREG-0161) 11
SAFETY RELATED MAINTEN.CE "MONrH: -*JUNE 1993 DOCKE..
O:
UNIT NAME:
50-272 SALEM 1 WO NO UNIT 870303031 1
870401080 1
920804147 1
931101002 1
DATE:
COMPLETED BY:
TELEPHONE:
JULY 10, 1993 R. HELLER (609)339-2212 EQUIPMENT IDENTIFICATION VALVE 16SW312 FAILURE DESCRIPTION:
VALVE MISSING -
REPLACE VALVE 12 SERVICE WATER HEADER PRESSURE ALARM FAILURE DESCRIPTION:
SERVICE WATER HEADER LOW PRESSURE ALARM COMES IN LOW -
RECALIBRATE BORIC ACID FLOW CONTROL INDICATION FAILURE DESCRIPTION:
1YIC110 FLOW CONTROL ERRONEOUS INDICATION -
INVESTIGATE VALVE 1WG41 FAILURE DESCRIPTION:
VALVE 1WG41 -
REBUILD ACTUATOR
10CFR50'. 59 EVALUATIONS-
' MON~H: -*JUNE 1993 DOCKE.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 SALEM 1 JULY 10, 1993 R. HELLER (609)339-2212 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
The Station Operations Review Committee has reviewed and concurs with these evaluations.
ITEM
SUMMARY
A.
Design Change Packages {DCPs) lEC-3208 Pkg 9 lEC-3208 Pkg 10 "Piping Gallery Area Ventilation Fire Damper Upgrade" -
The design scope for this package includes the replacement of existing fire dampers in the Piping Gallery Area Ventilation {SPAV)
System.
The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply except that seismic qualification for these dampers will be upgraded from non-seismic to seismic 2.
The basis for the Technical Specifications does not address the Fire Protection features or the Piping Gallery Area subsystem of the switchgear Penetration Area Ventilation system.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
{SORC 93-049)
"Salem Fire Damper Upgrade" -
The design scope for this package involves the application of a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (2 layer) fire wrap on four dampers on. the Diesel Fuel Oil Storage Area Ventilation (DFSAV)
Subsystem of the Diesel Generator Area Ventilation
{CAV) System Battery Rooms.
The function, basic configuration and operation of the system will not be altered and the codes, standards, qualification and design criteria of the original system will apply.
In order to maintain the integrity of the fire barrier, the dampers and duct work between the dampers and the fire barrier wall will be wrapped with a fire wrap material to obtain a fire rating equivalent to the barrier.
This DCP will also install two pairs of longitudinal braces to minimize the possible bending stresses on the Battery Room El. 100 1 exhaust air ductwork.
Longitudinal braces have been designed and will be installed as a modification to two existing supports, one on each end of the exhaust ductwork span, above the Battery Room ceiling.
The
10CFR5o'. 59 EVALUATIONS-
' MONTH: -'JUNE 1993 (cont'd)
ITEM lEC-3151 Pkg 1 B.
Safety Evaluations H-C-KC-MSE-0825 DOCKETtRO:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JULY 10, 1993 R. HELLER (609)339-2212 ductwork above the 64 1 El. Battery Room will have an access door installed as part of this modification to allow for easier access to reset the fire damper following periodic testing.
These modifications will not affect any margin of safety for the Diesel Fuel Storage Area Ventilation system or the Fire Protection system/features.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-049)
"Service Water Pipe for the Turbine Lube Oil Cooler" -
The carbon steel cement lined service water piping will be replaced with austenitic stainless steel 25% chromium 6% molybdenum.
Temporary Modification 91-075 is incorporated as a permanent change by this DCP.
This proposal does not reduce the margin of safety as defined in the basis for any Technical Specification.
The Technical Specifications has no applicability to service in the Turbine Building.
(SORC 93-055)
"Fire Water System" - The purpose of this 10CFR50.59 Review and Safety Evaluation is to determine whether the Salem Generating Station (SGS) fire water system represents an adequate backup fire suppression system for Hope Creek Generating Station (HCGS) without introducing a potential Unreviewed Safety Question for either SGS or HCGS.
Appendix A to Branch Technical Position APCSB 9.5-1 Section A.4, for SGS, requires that the original design of the fire suppression system meet single failure criteria.
As defined by the Branch Technical Position, a single failure, or crack in a line (for example) does not render both primary and backup fire suppression capability in an area inoperable.
The arrangement of the 10 inch interconnection does not meet this definition.
Therefore, the proposed temporary valve arrangement cannot be considered a permanent arrangement.
Based on a review of the HCGS and SGS Technical Specifications, the only
10CFR5o'. 59 EVALUATIONS-
. MONTH: -* JUNE 1993 (cont'd}
ITEM DES 93-0146 DOCKET-0:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JULY 10, 1993 R. HELLER (609)339-2212 information pertaining to fire protection is contained in Section 6.5 dealing with review and audit requirements for the Fire Protection Program and Section 6.9.3 dealing with Special Reports.
These do not involve the margins of safety.
Therefore, the proposed temporary valve alignment does not impact the margin of safety of any Technical Specification.
(SORC 93-051}
"Justification for Startup and Operation of Salem Units 1 & 2 11 The purpose of this evaluation is to provide justification for startup and operation of Salem Units 1 & 2 given all feasible scenarios that could be caused by the identified single failure.
This evaluation bounds operation with the Rod Control System in automatic (Mode 1 only}
as well as manual.
It is expected that while in manual rod control, the Operator will maintain cognizance of any rod movement and Tavg within the rod speed controller deadband of +/-1.5°F, consistent with the Precautions, Limitations, and Setpoints Document.
It has been demonstrated that Salem Units 1 & 2 continue to meet all safety limits, in the presence of the identified single failure.
It is important to note that, should the Rod Control System (RCS} failure event manifest itself, safe shutdown capability is maintained.
This RCS failure and subsequent RCCA withdrawal will have no affect on the availability, operability or performance of any safety related equipment required for accident mitigation.
As demonstrated in the evaluation, the regulatory design criteria and subsequent dose limits will continue to be satisfied.
In addition, the requirements of GDC 25 will continue to be satisfied.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
(SORC 93-054}
10CFR5o'. 59 EVALUATIONSe "MONTH:
~ JUNE 1993 (cont'd)
ITEM DOCKET-0:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
50-272 SALEM 1 JULY 10, 1993 R. HELLER (609)339-2212
- c.
Procedures and Revisions NC.NA-AP.ZZ-0024(Q)
"Radiation Protection Program" Rev. 2 -
The changes to the procedure are as follows: 1)
Removed Note 5.2.9 - use of ALNOR in place of RWP stay time -
page 12; 2) Corrected the 50.59 to remove tech spec section 6.12.2 interpretation discussion; 3) Removed choice of RPE or RP/C Manager from step 3.1, 1st bullet - page 2; 4)
Requires that Reg Guide 8.13 training be addressed in GET before procedure is implemented - cover page, and 5) Revised requirement to notify SNSS/NSS or SRPS of each issue of a LHRA key (step 5.2.11.d) to notify SNSS/NSS of each issue of a LHRS key to any area where operational plant changes could affect area dose rates.
For other areas, SRPS may be notified instead of SNSS/NSS -
page 14.
The changes made by this revision do not relate to the design criteria, specifications, or operation of the fuel cladding, RCS boundary, or containment, and do not address any margin of safety as defined in the basis for any Technical Specification.
(SORC 93-051)
~..
SALEM UNIT NO. 1 SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
UNIT 1 JUNE 1993 The Unit began the period operating at full power, and, with the exception of minor load reductions for condenser tube and waterbox cleaning, continued to operate at essentially full power until June 8, 1993, when a reactor trip occurred due to multiple circulating water pump trips and subsequent loss of condenser vacuum.
A sudden influx of matted grass caused high travelling screen pressure differentials which tripped the circulators.
The unit remained shutdown until June 18, 1993, while the rod control investigation continued.
on June 18, 1993, a reactor startup commenced.
The generator was synchronized to the grid on June 19, 1993, at 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br />.
Later the same day, the Unit was briefly taken offline at 0601 hours0.00696 days <br />0.167 hours <br />9.937169e-4 weeks <br />2.286805e-4 months <br /> to replace a faulty circuit card in the EHC system.
The card was replaced and the Unit synchronized at 0629 hours0.00728 days <br />0.175 hours <br />0.00104 weeks <br />2.393345e-4 months <br />, and a power escalation commenced.
The Unit was restored to full power on June 21, 1993, and with the exception of minor load reductions to address circulating water problems and fix a leaking heater drain pump flange, continued to operate at essentially full power throughout the remainder of the period.
REPUELING INFORMATION
.. MON'!'H:
..:.* JUNE 1993 MONTH JUNE 1993 DOCKET.O:
UNIT NAME:
DATE:
COMPLETED BY:
TELEPHONE:
- 1.
Refueling information has changed from last month:
YES NO X
50-272 SALEM 1 JULY 10, 1993 R. HELLER (609)339-2212
- 2.
Scheduled date for next refueling:
OCTOBER 2. 1993
- 3.
Scheduled date for restart following refueling:
DECEMBER 13, 1993
- 4.
a)
Will Technical Specification changes or other license amendments be required?:
YES NO ~~~-
NOT DETERMINED TO DATE ~~x~-
b)
Has the reload fuel design been reviewed by the Station Operating Review Committee?:
YES NO x
If no, when is it scheduled?:
5'.
Scheduled date(s) for submitting proposed licensing action:
N/A
- 6.
Important licensing considerations associated with refueling:
- 7.
Number of Fuel Assemblies:
- a.
Incore 193
- b.
In Spent Fuel Storage 656
- 8.
Present licensed spent fuel storage capacity:
1170 Future spent fuel storage capacity:
1170
- 9.
Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
September 2001 8-1-7.R4