LR-N970794, Monthly Operating Rept for Nov 1997 for Salem,Unit 1
| ML18106A208 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1997 |
| From: | Bakken A, Knieriem R, Todd F Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N970794, NUDOCS 9712180335 | |
| Download: ML18106A208 (12) | |
Text
e OPS~G Public Servide Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236
- Nuclear Business Unit U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn:
Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 Gentlemen:
DEC 12 1997 LR-N970794 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for November, 1997, is attached.
RBK/tcp Enclosures C
Mr. H. J. Miller A. C. Bakken III General Manager -
Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9712180335 971130 PDR ADOCK 05000272 R
PDR The power is in your hands.
I If If II f 1111 f llll)lll{lllll lllll[llt t!ll 95-2168 REV. 6/94 I
SALEM UNIT 1 NOVEMBER 1997 DOCKET NO.:
UNIT:
DATE:
COMPLETED BY:
TELEPHONE:
50-272 Salem 1 12/15/97 R. B. Knieriem (609) 339-1782 The unit is in a refueling and a steam generator replacement outage and remained shutdown for the entire period.
According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:
- Appropriately address long standing equipment reliability and operability issues.
After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
After the restart review, meet with the,, NRC and communicate the results of that review.
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 12/10/97 COMPLETED BY:
F. Todd TELEPHONE:
(609) 339-1316 OPERATING DATA REPORT OPERATING STATUS 1
Reporting Period NOVEMBER 1997 Hours in Report Period 2
Currently Authorized Power Level (MWt)
Max Dependable Capacity (MWe-Net)
Design Electrical Rating (MWe-Net) 3 Power level to which restricted (if any)
(MWe Net) 4 Reason For Restriction (if any)
This Month Yr To Date 5
No. of hours reactor was critical 6
Reactor reserve shutdown hours 7
Hours generator on l.ine 8
Unit reserve shutdown hours 0
0.0 0
0.0 9
Gross thermal energy generated (MWH) 0 10 Gross electrical energy generated (MWH) 0 11 Net electrical energy generated (MWH)
O 12 Unit Service Factor 13 Unit Availability Factor 14 Unit Capacity Factor (MDC) 0.0%
0.0%
0.0%
0 0.0 0
0.0 0
0 0
0.0%
0.0%
0.0%
15 Unit Capacity Factor (DER) 0.0%
0.0%
16 Unit Forced Outage Rate 100.0%
100.0%
17 Shutdowns scheduled over next 6 months (type, date, duration):
18 If shutdown at end of report period, estimated date of Startup:
Under Review 720 3411 1106 1115 None Cumulative 104380 0.0 100388 0.0 318062229 105301000 100148489 56.1%
56.1%
50.6%
50.2%
30.3%
DOCKET NO.:
UNIT:
DATE:
COMPLETED BY:
TELEPHONE:
OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS 50-272 Salem 1 12/10/97 F. Todd (609) 339-1316 MONTH NOVEMBER 1997 TYPE F=FORCED DURATION REASON NO.
DATE S=SCHEDULED (HOURS)
(1) 3859 11/1 F
720. 0 F, c 11/30 (1) Reason A -
Equipment Failure (Explain)
B - Maintenance or Test C -
Refueling D -
Regulatory Restriction E -
Operator Training/License Examination F - Administrative G - Operational Error (Explain)
H -
Other METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING CORRECTIVE POWER (2)
ACTION/COMMENT 4
Steam Generator Replacement (2) Method 1 - Manual 2 - Manual Trip 3 - Automatic Trip/Scram 4 -
Continuation 5 -
Other (Explain)
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 12/10/97 COMPLETED BY:
F. Todd TELEPHONE:
(609) 339-1316 AVERAGE DAILY UNIT POWER LEVEL MONTH NOVEMBER 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7 0
2'3,;,,..,,,*,, Q, 8
0 24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
16 0
DOCKET NO.:
UNIT:
DATE:
COMPLETED BY:
TELEPHONE:
SUMMARY
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH NOVEMBER 1997 50-272 Salem 1 12/15/97 R. B. Knieriem (609) 339-1782 The following items completed during November 1997 have been evaluated to determine:
- 1.
If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
- 2.
If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
'l~~ ;;-~> '"""'-'
- 3.
If the margin of safety as defined in the basis for any technical specification is reduced.
The 10CFR50. 59 Safety Evaluations showecf that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor.
These items did not change the plant effluent releases and did not alter the existing environmental impact.
The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
Design Changes Summarv of Safety Evaluations lEC-3399, Pkg. 1, Replacement Of Power Feeds For Unit 1 Vital Instrument Inverters.
This modification upgrades the normal feeder cables for the lA, lB, lC, and lD Vital Inverters by replacing them with cables of greater capability.
The original cables were adequate for the present loading, but do not have adequate capacity to support the rating of the inverters or for future growth.
This design change does not negatively~ impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lE~-03408, Pkg. 1, No. 15 Service Water Pump Replacement.
This design change replaces the No. 15 Service Water Pump with a pump manufactured of materials that are more resistant to the corrosive and erosive environment in which the pump operates.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does n~t involve an Unreviewed Safety Question.
lEC-3428, Pkg. 1, Main Turbine LUhe Oil Evactor Drain Piping Modification.
This design change modifies the Unit 1 Main Turbine Lube Oil reservoir evactor and demister drain piping to prevent discharge of oil vapors directly to the waste water tank and to ensure drainage of oil removed by the demister.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of eitqer an accident or a malfunction.of equipment' importantf.6.safety.".Therefore, this design change does c.not involve* an Unreviewed Safety Que~t,ioI1: '.
,,,,.,.. 1 lEC-3472, Pkg. 1, No. 11 and No 12 RHR Pump Recirculation Flow High Setpoint Change.
This design change modifies the closing setpoint for the RHR minimum flow valves (11RH29 and 1RH29) from 1000 gpm to 1150 gpm.
This is necessary to eliminate inadvertent cycling of these valves.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lEC-1242, Pkg. 1, Salem Unit 1 Penetration Area Blowout Panel Modifications.
This design change implemented modifications which resolved obstructions and degraded material conditions in the pressure relief path.
This design change does not*negatively impact any accident response.
This design cha~ge does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. *Therefore, this design change does not involve an Unreviewed Safety Question.
lEq-3530, Pkg. 1 & 2, Cavitation/Debris Mitigation On Safety Injection And Charging/Safety Injection Lines.
This modification adds flow resistance orifices to each of the four Safety Injection system hot and cold legs down stream of existing throttle valves to prevent valve cavitation and seat erosion due to high differential pressure across the valves.
Additionally, this modification adds flow resistance orifices to each of the four Charging/Safety Injection system cold legs upstream of existing throttle valves.
These orifices will transfer much of the required pressure drop from the existing valves and allow the valves to be opened to a position in which post-LOCA debris will not block the valve opening.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
.(
,, -~* * ~*,.,-
';-~
,r,;,
I
- \\ ~ '*, '*'
lEC-3531, Pkg. 1, RVLIS.Mid~loop-Wide Range Level Upgrade.
This design change installs a new wide range Mid-loop level transmitter, toggle switch, and. indicator to provide level indication during reduced inventory conditions and during vacuum fill.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lEC-3662, Pkg. 1, Component Cooling Water (CCW) Letdown Temperature Control Valve (CC71) Modification.
This design change modifies the design and operation of the Letdown Heat Exchanger Temperature Control valve (1CC71) to ensure a minimum safeguards alignment for the CC System under single failure conditions and to preclude a potential Component Cooling Water pump runout condition.
The changes will also ensure that letdown can be restored to an alternate shutdown condition following a fire.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lEq-3668, Pkg. 13, Generic Letter 96-06 Modifications.
This design change brings Salem Unit 1 into conformance with the Salem SAR and SER to eliminate the potential for two-phase flow, voiding, water hammer, and thermally induced overpressure in the Containment Fan Coil Unit Service Water piping.
This package evaluates the interim plant conditions during installation of the modification.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lEC-3668, Pkg. 16, Generic Letter 96-06 Modifications.
This modification package performs a Service Water pump coastdown test following modifications made under Packages 1, 2, 3, 4, 5 I 6 I 7 I 8 I 9 I 10 I 11 I 12 I 13 I 15 I and 19.
. This design change does not negatively impact any accident response.
This design change does not increase the p:i;opab~lity. qr c9nseqµ@I?-<;;:,E?s,,gf, ~tt~~r. an a.cs::~de~t. <?!. a malfunction of equipment --important to safety.
Therefore I this design change does not. involve... an Unreviewed Safety
,c.f.,
1
- .-.1,1
.*\\.*
1*..* r.**..,*.~,1.* *,,
- .,;~
'.\\...,!;_.
,_),\\.;
~-*.,1.~.
QueStlOn.
lEE-0348, Pkg. 1, Anti-sweat Insulation For Containment Fan Coil Unit Service Water Piping.
This design change installs anti-sweat insulation on the 3" diameter and 3/4" diameter Service Water piping and replaces the insulation on the 2" diameter Service Water motor cooler piping associated with the Containment Fan Coil Units located at Elevation 130'-0 of the Salem Unit 1 Containment Building.
The change alleviates condensation :that.. has c.aused equipment corrosion damage.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lEE-0333, Pkg. 6, Replace Service Water Pump Strainer Backwash Valve.
This *modification replaces.the existing Service Water pump strainer backwash diaphragm valve (16SW24) *with a ball valve *which has' a longer service life between preventive maintenance and is better suited for the frequent cycling of backwash service.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a
e e
malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
lEE-0371, Pkg. 1, Modify Controls To The 1CH168 Valve.
This modification eliminates a single failure vulnerability concern related to the 1CH168 valve (Temperature Control Isolation Valve in the Emergency Air Conditioning System).
Failure of this valve to open could lead parts of the combined Control Room envelope to exceed temperature limits imposed by section 3.11 of the UFSAR. This modification will be accomplished by permanently removing the pneumatic control to the valve and*permanently placing the valve in the full open position.
This design change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
Temporary Modifications Summary of Safety Evaluations There were no changes in this category implemented during November, 1997.
Procedures Summary of Safety Evaluations Sl.OP-IO.ZZ-0009 {Q), Revision 5,, Defueled To Mode 6, and Sl.OP-SO.WG-0006{Q), Revision 8, Containment Purge To The Plant Vent.
This evaluated the use of Sl.OP-IO.ZZ-0009(Q) and Sl. OP-SO. WG-0006 (Q)
.~'as ii:;". fqr the Salem Unit 1 cycle 13 core reload inside containment. The safety evaluation determines that post-accident offsite and control room dose consequences are not increased and remain within the acceptance criteria given in Standard Review Plan Section 15.7.4 and GDC-19 if a fuel handling accident inside containment occurs when a containment purge is in progress with no CFCU's operating and without prompt containment isolation.
This procedure revision does not negatively impact any accident response.
This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this procedure revision does not involve an Unreviewed Safety Question.
Emergency Plan, Section 3, Revision 11.
This revision to the Salem and Hope Creek Emergency Plan changes the Emergency Response organization by eliminating a Duty Emergency Response Organization member at the Control Point~
by having a Support Emergency Response member at the
Te9hnical Support Center, and by having the unaffected station's Radiation Protection Supervisors report to the affected station upon an Alert or higher event classification.
This procedure revision does not negatively impact any accident response..
This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this procedure revision does not involve an Unreviewed Safety Question.
NC.DE-AP.ZZ-0004(Q), Design Drawings.
The proposed change involves nomenclature and responsibility changes related to the process for controlling engineering design drawings.
This UFSAR change does not negatively impact any accident response.
This design change does not increase the probability or* consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
UFSAR Change Notices Summary of Safety Evaluations
- ~ "
'.\\
~.
r.-.,.
UFSAR Change Notice 97-099.
The UFSAR change revises SGS-UFSAR Sections 12.1.3.1.1, "Primary and Secondary Neutron Sources," and 12.1. 3.1.. 2,.. _'~Primary.Source Data," to incorporate additional information associated with new neutron sources for use in*-Salem.. Unit 1 cycle 13.
This UFSAR change does not negatively impact any accident response.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Therefore, this design change does not involve an Unreviewed Safety Question.
Deficiency Reports Summary of Safety Evaluations Other There were no changes in this category implemented during November, 1997.
Summary of Safety Evaluation Safety Evaluation DSl.8-0042.
Salem Unit 1 Cycle 13 Reload This review evaluated the reconfiguration and refueling of the Salem Unit 1 Cycle 13 reload for Mode 6 operation.
This evaluation does not negatively impact any accident response.
This procedure*revision does not increase the probability or consequences of either an accident or a
ma~function of equipment important to safety.
Therefore, this procedure revision does not involve an Unreviewed Safety Question.