ML18106A271
| ML18106A271 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/31/1997 |
| From: | Bakken A, Knieriem R Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N98016, NUDOCS 9801260429 | |
| Download: ML18106A271 (16) | |
Text
~ublic SE1rvice Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit LR-N98016 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:
In compliance with Sectfrm 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original monthly operating report for December, 1997, is attached.
I Sincerely, General Manager -
Salem Operations RBK/tcp
/~.I Enclosures c Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046
- ~------- - - - - --- -- ------ - -~ --- - - ~--- --~
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- The power is in your hands.
95-2168 REV. 6/94
- DOCKET NO.:
UNIT:
- 50-272 Salem 1 DATE: 1/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782 MONTHLY OPERATING
SUMMARY
MONTH DECEMBER 1997 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 NRG and communicate the results of that review.
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 01/09/98 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period DECEMBER 1997 Hours in Report Period 744 2 Currently Authorized Power Level (MWt) 3411 Max Dependable Capacity (MWe-Net) 1106 Design Electrical Rating (MWe-Net) 1115 3 Power level to which restricted (if any) (MWe Net) None 4 Reason For Restriction (if any)
This Month Yr To Date Cumulative 5 No. of hours reactor was critical 0 0 104380 6 Reactor reserve shutdown hours 0.0 0.0 0.0 7 Hours generator on line 0 0 100388 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 0 0 318062229 10 Gross electrical energy generated (MWH) 0 0 105301000 11 Net electrical energy generated (MWH) 0 0 100148489 12 Unit Service Factor 0.0% 0.0% 55.8%
13 Unit Availability Factor 0.0% 0.0% 55.8%
14 Unit Capacity Factor (MDC) 0.0% 0.0% 50_.4%
15 Unit Capacity Factor (DER) 0.0% 0.0% 50.0%
16 Unit Forced Outage Rate 100.0% 100.0% 30.7%
17 Shutdowns scheduled over next 6 months (type, date, duration):
18 If shutdown at end of report period, estimated date of Startup: Under Review
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 01 /09/98 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH DECEMBER 1997 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F=FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S=SCHEDULED (HOURS) (1) POWER (2) ACTION/COMMENT 3859 12/1 F 744 F,C 4 Steam Generator
- Replacement and 12/31 Refueling Outage (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip C - Refueling 3 - Automatic Trip/Scram D - Regulatory Restriction 4 - Other E - Operator Training/License Examination F - Administr13tive G - Operational Error (Explain)
H - Other
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 01/09/98 COMPLETED BY: F. Todd TELEPHONE: (609) 339-1316 AVERAGE DAILY UNIT POWER LEVEL MONTH DECEMBER 1997 DAY AVERAGE DAILY POWER DAY AVERAGE DAILY POWER LEVEL* (MWe-Net) LEVEL (MWe-Net) 1 0 17 Q 2 Q 18 0 3 Q 19 Q 4 0 20 0 5 Q 21 Q 6 Q 22 0 7 Q 23 Q 8 Q 24 0 9 0 25 0 10 0 26 Q 11 0 27 Q 12 Q 28 0 13 0 29 Q 14 0 30 Q 15 Q 31 0 16 0
- DOCKET NO.:
UNIT:
50-272 Salem 1 DATE: 1/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782
SUMMARY
OFCHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH DECEMBER 1997 The following items completed during December 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
- 3. If the margin of safety as defined in the basis for any technical specification is reduced.
The 10CFR50.59 Safety Evaluations showed 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 Summary of Safety Evaluations 1EC-3191, Pkg. 1, Turbine Driven Auxiliary Feed Pump(TAFP) Recirculation Relief Valve Modification. This modification installs a new pressure relief valve on the TAFP continuous recirculation line to re-establish over pressure protection for the 13 TAFP Woodward Governor/Turbine Bearing Jacket coolers.
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.
1EC-03237, Pkg. 1, No. 15 Service Water Pump Replacement. This design change replaces major portions of the cement lined carbon steel Turbine Building Service Water piping with 6% molybdenum austenetic stainless steel piping material.
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.
1EC-3329, Pkg. 1, 14 Service Water Pump (1SWE4) Replacement Modification. This design change replaces Service Water pump 1SWE4 with a pump that is manufactured of materials that are more resistant to the corrosive, erosive, and silt laden river water present in the Service Water system.
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.
1EC-3349, Pkg. 1, Relocation of 12 Containment Fan Cooler Unit (CFCU)
Return Flow Control Valve 12SW223. This design change relocates the Service Water CFCU return flow control valve 12SW223 away from the 12SW76 stop valve to eliminate cavitational damage to 12SW76 caused by the throttling affect of 12SW223.
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.
1 EC-3390, Pkg. 1, Addition of Time Delay for 1 H Group Bus Undervoltage.
This design change provides a time delay of 0.30 seconds in the undervoltage reactor trip circuit to prevent spurious reactor trips from momentary electrical power transients.
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.
1 EC-3390, Pkg. 2, Addition Of Time Delay For 1 E Group Bus Undervoltage.
This design change interposes an external time delay element on the 4KV group bus 1E undervoltage trip to prevent spurious reactor trips from momentary electrical power transients.
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.
1EC-3390, Pkg. 3, Addition Of Time Delay For 1 F Group Bus Undervoltage.
This design change interposes an external time delay element on the 4KV group bus 1F undervoltage trip to prevent spurious reactor trips caused by momentary electrical power transients.
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.
1 EC-3390, Pkg. 3, Addition Of Time Delay For 1G Group Bus Undervoltage.
This design change interposes an external time delay element on the 4KV group bus 1G undervoltage trip to prevent spurious reactor trips caused momentary electrical power transients.
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.
1 EC-3405, Pkg. 1, Salem Unit 1 Waste Gas Analyzer Panel Backfit. This design change upgrades instrumentation and controls on Waste Gas Analyzer panel 110-1 and makes it identical to Waste Gas Analyzer Panel 110-2, which is the corresponding Unit 2 panel.
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.
1EC-3407, Pkg. 1, 11 Service Water Pump (1SWE1) Replacement Modification. This design change replaces Service Water pump 1SWE1 with a pump that is manufactured of materials that are more resistant to the corrosive, erosive, and silt laden river water present in the Service Water system ..
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.
1EC-3409, Pkg. 1, 16 Service Water Pump (1SWE6)Replacement Modification. This design change replaces Service Water pump 1SWE1 with a pump that is manufactured from materials that are more resistant to the corrosive, erosive, and silt laden river water present in the Service Water system ..
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.
1EC-3417, Pkg. 1, 28 VDC Circuit Breaker Replacement. This design change replaces the 28 VOC Circuit Breakers, cables, and time delay relays to reduce the voltage drop associated with control power and indication in auxiliary system circuits. The modification enhances the voltage availability such that the margin of voltage available at the 28 VOC auxiliary system components and devices will improve, increasing system reliability and performance.
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.
1 EC-3486, Pkg. 1, 10CFR50 Appendix R Alternate Shutdown Methodology -
Installation Of Transfer Switches. This design change installs local switches in motor control center and control panel circuits for 34 components (3 chillers, 15 valves, 4 vent fans, 8 room coolers, and 4 pumps) to allow isolation of component wiring from the Control Room, Relay Room, and ceiling area of the 460/230V Switchgear Room. This will preclude the necessity of electrical rewiring and jumper installation to operate those components to achieve Hot Standby in the event of a fire in those areas.
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.
1 EC-3486, Pkg. 2, 10CFR50 Appendix R Alternate Shutdown Methodology -
Installation Of Transfer Switches. This design change installs local switches in motor control center and control panel circuits for 1O valves to allow isolation of component wiring from the Control Room, Relay Room, and ceiling area of the 460/230V Switchgear Room. This will preclude the necessity of electrical rewiring and jumper installation to operate those components to achieve Hot Standby in the event of a fire in those areas.
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.
1 EC-3495, Pkg. 2, Steam Trap Replacement Project. This design change installs a restricting orifice, a strainer, and a bypass valve in lieu of a steam trap in the Main Steam system to reduce the potential of dumping excessive quantities of steam into the condenser when steam traps are bypassed due to trap failure. The modification will also minimize the contribution of Main Steam piping condensate removal systems to the Reactor Coolant system excess cooling phenomenon.
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.
1EC-3607, Pkg. 1, Pressurizer Overpressure Protection System (POPS)
Relief Valves (1 PR1/1 PR2) Circuit Modification. This design change modifies the POPS control circuitry to permit manual action by the operator to open or close the POPS relief valves even when POPS is armed.
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.
1EC-3622, Pkg. 1, Liquid Radwaste System Enhancements. This modification installs a Tubular Ultra Filtration system (TUF) unit to reduce the radioactivity released in liquid effluent.
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.
1 EC-3648, Pkg. 1, SSPS Phase A and Containment Ventilation Isolation Modification. This modification installs relays and switches to provide the capability to manually initiate either Containment Ventilation or Containment Phase A Isolation individually when required. The previous configuration provided a single switch which initiated a manual isolation of both Containment Ventilation and Containment Phase A Isolation valves simultaneously.
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.
1EC-3668, Pkg. 4 and 5, 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 safety evaluation evaluated the interim plant conditions during installation of the modifications under 1EC-3668.
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.
1EC-3668, Pkg. 8, Generic Letter 96-06 Modifications, Service Water System 11 Header Check Valve Installation. This modification installed a redundant check valve in the 11 Service Water Nuclear header Containment Fan Coil Unit (CFCU) 16" supply piping downstream of existing check valve 11 SW51. This check valve will prevent drainage of the 11 and 12 CFCU's supply piping in the event of check valve 11 SW51 failure.
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.
1 EC-366_8, Pkg. 19, Generic Letter 96-06 Modifications, Service Water System CFCU Thermal Overpressure Protection. This modification installed a 1" bypass line for each of the five CFCU Service Water return lines. This will eliminate the potential for overpressure in the fan coils in the event of a Loss of Offsite Power (LOOP) associated with a Main Steam Line Break (MSLB) or Loss of Coolant Accident (LOCA).
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.
1EC-3696, Pkg. 1, 1 PR1 and 1 PR2 Power Operated Relief Valve (PORV)
Control Modifications. This design change modified the PORV control circuitry to provide separation/isolation of safety-related from non-safety-related functions to prevent a credible single failure from affecting both PORV's. This change supports* License Amendment 194 to credit the PORV's for inadvertent safety injection.
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.
1EA-1242, Pkg. 2, Salem Unit 1 Steam Generator (SG) Replacement Project:
Steam Generator Slowdown Sample Line Modification. This modification installed a grab sample valve and a portion of the tubing and tube tray for the SG Slowdown sample line. The original SG (Model 51 SG) sample tubing was located in painted and insulated carbon steel tube tray. A portion of the tubing and tube tray were removed from each Model 51 SG in order to effect the SG replacement with an unused Model F SG.
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.
1EA-1273, Pkg. 1, Salem Unit 1 Steam Generator (SG) Replacement Project.
This modification replaced the original SGs (Model 51 SG) with Model F SGs.
The replacement Model F SGs are similar in design to the Model 51 SGs not withstanding the number of tubes and differences in system connection points and other appurtenances.
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.
1EE-0027, Pkg. 1, 13 Charging Pump Packing Seal Tank Overflow Line Flowmeter and Flow Totalizer Installation. This modification installed a turbine flowmeter and a digital flow totalizer on the 13 Charging Pump packing seal tank overflow line. The installed instrumentation will be used to measure*
pump seal leakage so that this leakage can be classified as an identified leakage.
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.
1 EE-0034, Pkg. 1, Circulating Water Standpipe Sample Pump Upgrade. This modification upgrades the Circulating Water Standpipe Sample pumps to enhance the reliability and maintainability of the chlorination system.
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.
1EE-0066, Pkg. 1, 11A Circulating Water Traveling Screen Modifications.
This modification upgrades the 11A Circulating Water Traveling Screen to improve reliability and performance.
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.
1 EE-0067, Pkg. 1, 118 Circulating Water Traveling Screen Modifications.
This modification upgrades Circulating Water Traveling Screens to improve reliability and performance.
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.
1EE-0151, Pkg. 1, Protection Of Condensate Piping From Over Pressurization. This modification added a relief valve to protect piping and equipment from over pressurization when the Condensate pump is isolated.
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.
1EE-0159, Pkg. 1, Local Pressure Gauges - Seismic Mounting. This modification was performed to enhance and qualify supports for various non-safety related pressure gauges in the Chemical and Volume Control, Service Water, Residual Heat Removal, Control Air, Chilled Water, Component Cooling, Safety Injection, Containment Spray, and Auxiliary Feedwater systems to conform to Seismic Class 1 criteria.
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 Un reviewed *Safety Question.
1EE-0161, Pkg. 1, Coating For CFCU Cooling Coil And Motor Cooler Water Boxes. This modification implemented the refurbishment of the corrosion deteriorated CFCU cooling coil and motor cooler water boxes by either repair or
~eplacement of water box components and the application of a protective coating to resist further corrosion.
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.
1EE-0176, Pkg. 1, Disconnect Motor Operated Valve (MOV) Heaters From 13 MAC Distribution Panel. This modification removed power to the motor heaters on MOV's. The MOV heaters are non-safety related, unqualified, and not required to maintain environmental qualification. Prior to this modification the breakers for these heaters were tagged open. Disconnection of the heaters will eliminate the need for plant staff to periodically evaluate the necessity to keep or remove the tags as required by the tagging procedure.
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.
1EE-0196, Pkg. 1, 11 Reactor Coolant Pump (RCP)Seal Injection Flow Transmitter Replacement . This modification replaced the original equipment Seal Injection Flow transmitter (1FIT144) with a Rosemount 3051 C "Smart" Model transmitter.
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.
1EE-0333, Pkg. 2, Replace Service Water Pump Strainer Backwash Valve 12SW24. This modification replaced the existing Service Water pump strainer backwash diaphragm valve (12AW24) 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 malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
1EE-0335, Pkg. 1, Main Steam Coil Drain Tank (MSCDT) Discharge Line Check Valve Additions. This modification installed check valves in the drain lines from the MSCDT to the sixth point (No. 16) Feedwater heaters and
replaced small sections of carbon steel pipe with chrome molybdenum pipe to support the erosion/corrosion program.
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.
1EE-0349, Pkg. 1, Circulating Water Pump Bearing Lubrication Relief Valve Replacement. This modification replaces the relief valve in the Circulating Water pump bearing lubrication water pump header with a newer model relief valve of increased size and with increased set pressure.
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.
1EE-0350, Pkg. 1, 12 Service Water Pump Replacement. This modification replaced the 12 Service Water pump with an upgraded pump that is interchangeable with the existing pumps.
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 December, 1997.
Procedures Summary of Safety Evaluations S1 .OP-SO.RC-0002(Q), Reactor Coolant System (RCS) Vacuum Refill System. This evaluated procedure S1 .OP-SO.RC-0002(Q) prior to its use to vacuum fill the RCS.
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.
J.I ' ....
UFSA~ Change Notices
- Summary of Safety Evaluations UFSAR Change Notice 97-130. The UFSAR change revises SGS-UFSAR Sections 6.3.2, to add clarification of Emergency Core Cooling system (ECCS) modes of operation by including the hot leg flowpath from the RHR pump. The hot leg flow path from the RHR pump was previously removed from the UFSAR when it was eliminated in the Emergency Operating Procedures (EOP) for a LOCA occurring in Modes 1-3.
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 Notice 97-133. The UFSAR change shifts reporting relationships for the Salem Operations Organization and changes the management title for the Salem Chemistry Department without introducing any new or deleting any former responsibilities. It also revises the station succession of authority.
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 There were no changes in this category implemented during December, 1997.
Other Summary of Safety Evaluation Safety Evaluation S97-137. Nuclear Engineering Reorganization. This review evaluated the organizational changes imposed by the December 1997 engineering reorganization.
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 malfunction of equipment important to safety. Therefore, this procedure revision does not involve an Unreviewed Safety Question.