Safety Evaluation Supporting Revised Procedure OP-3140, Providing Technically Acceptable Actions During Degraded Grid Voltage Conditions W/O LOCA to Assure Protection of Class 1E Electrical Sys & EquipmentML20155B835 |
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Vermont Yankee ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
03/31/1986 |
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From: |
Office of Nuclear Reactor Regulation |
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To: |
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Shared Package |
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ML20155B828 |
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References |
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NUDOCS 8604160370 |
Download: ML20155B835 (4) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program ML20216F1001998-04-15015 April 1998 Safety Evaluation Accepting 980331 Licensee Proposal to Perform Alternative Testing for Containment Pressurization Test for Vynp ML20217F3421998-03-25025 March 1998 SER Accepting Plans for 1998 & 1999 Refueling Outages Re Reactor Vessel Internals for Plant ML20212H1521998-03-0606 March 1998 Correction to Page 7 of SE Re Relief Request for Third 10-yr Interval Pump & Valve IST Program for Plant ML20217N4911998-02-27027 February 1998 SER Pertaining to Cracking of EDG Lube Oil Piping at Vermont Yankee ML20198P9941998-01-15015 January 1998 SE Authorizing Relief Requests for Third Interval Pump & Valve Inservice Testing Program ML20141A4151997-06-18018 June 1997 Revised SE Accepting Proposed Onsite Disposal of Slightly Contaminated Silt Removed from Vermont Yankee Cooling Towers ML20135E5401997-03-0303 March 1997 Safety Assessment Accepting Mod of RHR & CS Sys Containment Isolation Function Configuration ML20134N8271996-11-20020 November 1996 Safety Evaluation Accepting Licensee Scope & Insp Methods Proposed for Insp of Core Spray Internal Piping During Fall 1996 Refueling Outage at Plant ML20134F9631996-11-0505 November 1996 Safety Evaluation Re Power/Flow Exclusion Region Calculation Method Using LAPUR5 Computer Code & Implementation of Solomon Stability Monitor for Licensee Facility ML20128N3531996-10-11011 October 1996 Safety Evaluation Accepting Licensee Flaw Evaluation of Indication Found During Reactor Pressure Vessel Insp at Plant ML20129G3611996-10-0202 October 1996 Safety Evaluation Accepting Proposed Repair for Plant Core Shroud ML20057A6991993-09-0303 September 1993 Safety Evaluation of IST Program Relief Requests for Pumps & Valves for Third 10-yr Insp Interval ML20057A2791993-08-12012 August 1993 Safety Evaluation Accepting Licensee Reasons Given for Delay in Completing short-term Actions Requested in Ieb 93-003, Resolution of Issues Re to Rv Water Level Instrumentation in Bwrs ML20246D7731989-08-21021 August 1989 Safety Evaluation Supporting Util Response to Generic Ltr 83-28,Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events. Equipment Classification Program for safety-related Components Acceptable ML20244D0311989-06-0707 June 1989 Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan ML20205T4181988-10-14014 October 1988 Errata to Safety Evaluation Concluding Util Submittal Re Spent Fuel Pool Expansion ML20204F7271988-10-14014 October 1988 Safety Evaluation Supporting Proposed Expansion of Spent Fuel Pool at Facility ML20236N6461987-08-0707 August 1987 Safety Evaluation Re Permanent Elimination of Liquid Penetrant Exam of Feedwater Nozzles at Facility.Due to Lack of Reasonable Assurance That Ultrasonic Exam Can Totally Replace Penetrant Exam,Request Unacceptable ML20214T9891987-05-28028 May 1987 Safety Evaluation Re Util 870112 Proposed Plans to Inspect Two Overlay Repaired Core Spray safe-ends in Lieu of Replacement During Upcoming 1987 Refueling Outage.Plans Acceptable,Providing That Insp Results Satisfactory ML20207S7801987-03-12012 March 1987 Safety Evaluation Granting Relief from Tech Spec 4.7.A.3 on one-time Basis to Perform RHR Pump Wear Ring Replacement ML20214T4921986-11-24024 November 1986 Safety Evaluation Accepting Licensee 830511 & 860117 Responses to Generic Ltr 83-08 Re Mod of Vaccum Breakers on Mark I Containments ML20215M5871986-10-24024 October 1986 Preliminary Evaluation of Containment Study Transmitted w/860902 Ltr.Licensee Estimates Appear Optimistic Considering Uncertainties Inherent in Failure Rate Data ML20206F3651986-06-16016 June 1986 Safety Evaluation Re Proposed Repair of Core Spray safe- Ends,During Current Refueling Outage.Plant Can Be Safely Returned to Power Operation After Satisfactory Completion of Core Spray safe-end Repairs ML20206F0681986-06-13013 June 1986 Safety Evaluation Supporting 850514,0710,860327,0411 & 0513 Requests for Approval to Use Pvrc Damping Values (ASME Code Case N-411) for Piping Sys Reanalysis ML20202J4211986-03-31031 March 1986 Safety Evaluation Accepting Util Design Mods & Tech Spec Changes Re Degraded Grid Voltage Protection for Class 1E Sys.Lll Technical Evaluation Rept Encl ML20155B8351986-03-31031 March 1986 Safety Evaluation Supporting Revised Procedure OP-3140, Providing Technically Acceptable Actions During Degraded Grid Voltage Conditions W/O LOCA to Assure Protection of Class 1E Electrical Sys & Equipment ML20140H9881986-03-25025 March 1986 Safety Evaluation Re Util 851008 Request to Install Carpet Over Vinyl Asbestos Tiled Control Room Floor Covering. Installation of Carpet Will Not Decrease Level of Fire Safety in Control Room & Deviation Acceptable ML20138E4201985-12-0202 December 1985 Safety Evaluation Supporting Util 831107 & 840320 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability ML20136F1241985-11-18018 November 1985 Safety Evaluation Re IE Bulletin 80-11, Masonry Wall Design. Issues Re Arching Action Theory Resolved ML20137S7331985-09-27027 September 1985 Safety Evaluation Approving Use of Fuel Thermal Performance Code,Frosstey,For Analysis of LOCA Conditions at Low & Moderate Burnups ML20135C8921985-09-10010 September 1985 Safety Evaluation Supporting 840824 Commitment to Convert Air Containment Atmosphere Dilution Sys to Nitrogen Sys,In Response to Generic Ltr 84-09 ML20135C9121985-09-10010 September 1985 Safety Evaluation Supporting Conclusion That Diversification of Scram Discharge Vol Level Instrumentation Not Necessary & Tech Specs,As Modified in Amend 76,resolve Staff Concerns Re Need for Instrumentation Diversity ML20134K7351985-08-19019 August 1985 Safety Evaluation Accepting 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing ML20136G3611985-08-12012 August 1985 Safety Evaluation Accepting Seismic Design Criteria Utilized for Evaluation of Modified Recirculation Sys ML20132D8971985-07-22022 July 1985 Safety Evaluation Supporting Use of Pvrc Damping Values (ASME Code Case N-411) for Response Spectrum Seismic Piping Analyses ML20127D8991985-05-0606 May 1985 Safety Evaluation Re 840925 & 1002 Responses to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review Program & Procedures.Program & Procedures Acceptable 1999-09-17
[Table view] Category:TEXT-SAFETY REPORT
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Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core 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N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review 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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO PROCEDURES FOR DEGRADED
- GRID VOLTAGE PROTECTION FOR CLASS 1E l POWER SYSTEMS FOR FACILITY OPERATING LICENSE NO. DPR-28 VERMONT YANKEE NUCLEAR POWER CORPORATION VERMONT YANKEE NUCLEAR POWER STATION DOCKET NO. 50-271 INTRODUCTION ,
The on-site alternating current (AC) safety class IE electric system is supplied!
i power-from either the off-site transmission grid or from the on-site standby emergency diesel generators (EDG). During normal plant operating conditions, 4
the class'1E busses are supplied power from the transmission grid. Should the grid voltage degrade and become low enough so that the voltage at the class IE equipment is below its qualified operating voltage, equipment damage could occur.
The NRC requested that the licensee address thi.: degraded voltage condition by responding to NRC Generic Letter dated June 3, 1977. The generic letter requested the licensee to analyze the class IE system to determine the grid voltage at
, which damage could occur. As a result, the licensee made plans to install
' voltage sensing devices on the class 1E busses with coincident logic and with the low voltage set point above a value where equipment damage could occur.
This voltage device would then cause the off-site grid supply to be disconnected from the class IE system at voltages below this value. The class IE busses would then be supplied power from their respective emergency diesel generators.
However, New England licensees were concerned that significant degradation of the grid would result if automatic disconnection occurred as a result of the large number of nuclear plants in the New England area. It was their view that automatic disconnection from the grid should only be required if a low grid voltage occurred at the same time as a loss of Coolant Accident (LOCA). They i agreed that should their plant have a LOCA at the same time there was a degraded grid voltage condition, they would automatically disconnect from the off-site grid. The emergency diesel generators would then supply power to the class IE systems. However, if there was a degraded grid voltage condition l
without a LOCA the operator would take the necessary manual action to protect the class 1E system.
i 8604160370 860331 PDR ADOCK 05000271' p PDR w.
Safety Evaluation 2 This proposal has been reviewed and accepted by the NRC with the condition that the licensee develop an operating procedure to provide the necessary operator guidance to protect the Class 1E system under degraded grid _ voltage conditions without a LOCA condition. By letter dated November 2, 19B4, the licensee submitted to the staff a draft operating procedure OP-3140 Low Grid Voltage Without An Accident Signal, Alarm Annunciator Response Procedure and further stated that the final procedure would be available for review onsite.
This safety evaluation provides the staffs review of the acceptability of the licensee's procedures to provide the necessary operator guidance to protect the Class 1E systems under a degraded grid voltage condition without a concurrent LOCA.
Discussion Procedure OP-3140 was reviewed with the licensee during the staff's inspection conducted at the facility October 7 - 11, 1985. (Refer to Inspection Report No. 50-271/85-29). During this review the staff recommended procedural changes to clarify and aid operator decision making. These recommendations primarily involved establishing time limitations during which operator action is required .
for each level of degraded voltage in the procedure. These changes were agreed '
to by the licensee. In a letter to the NRC dated January 22, 1986, the licen-see agreed to implement the subject degraded grid voltage procedure prior to restart from the 1985/1986 outage.
Procedure OP-3140 provides two degraded grid undervoltage levels (3700 volts and 3600 volts) at which operator actions are to be taken to assure protection of. Class 1E electrical equipment to avoid possible damage from low voltage.
The basis for selection of these two undervoltage levels is presented in a study "YAEC 1205 Auxiliary Power Systems Voltage" which was transmitted to the NRC by letter dated March 17, 1980.
Degraded Grid Voltage at 3700 40 volts re connected to each of the 4160 volt Two undervoltcge emergency buses (3 sensing) and 4 . relay circuitsThe relays u these circuits are calibrated to actuate when the bus voltage decays to 3700 140 volts. Actuation of any one or more of the relays will actuate a low voltage alarm in the main control room following a 10 secnr.d time delay. (The time delay prevents nuisance alarms from short term operating voltage transients such as those caused by starting a large motor).
Procedure OP-3140 requires imediate operator action upon receipt of the de-graded bus alarm. The operator is required to contact the Rhode Island, East-ern Massachusetts and Vermont Energy Control Center (REMVEC) systems operator to request assessment of the degraded grid condition and that appropriate ac-tions be taken to restore the grid to normal voltage. If the grid voltage is w.
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Safety Evaluation 3 not restored sufficiently to clear the degraded grid alarm within 15 minutes, the operator is required to start the emergency diesel generators, open the electrical grid breakers to the emergency buses and power them from the diesel generators.
Degraded Grid Voltage at 3600 Volts or Lower Procedure OP-3140 requires the operator to monitor the voltage following receipt of the low voltage alarm at 3700 volts. If the voltage decays to 3500 volts or lower at any time, the operator immediately starts the emergency diesel generators and connects the emergency buses to them without delay.
Additional circuitry has been provided to automatically power the emergency buses from the diesel generators if a degraded grid voltage alarm occurs coincident with an ESF actuation. Additional circuitry also provides for automatic load shedding if a diesel generator circuit breaker opens during a loss of off-site power condition. It includes automatic reclosing of the diesel generator circuit breaker and sequencing essential loads onto the emergency' bus. . 5 Evaluation The Vermont Yankee degraded grid voltage protection system and operating pro-cedure OP-3140 enhances overall plant safety in the following ways.
-- The operator is warned of a voltage decay on the emergency buses at a voltage level (3700 volts) that permits continuei operation of the plant without degradation of safety related electrical equipment. However if continued for a long period of time or if further significant voltage degradation were to occur equipment damage or mal-operation could be a problem. The warning alarm provides the operator time to assess the situation, attempt to correct it, and if correction is not imminent it allows time for an orderly transition of the 1E safety loads to the emergency diesel generators.
-- If the voltage drop is to a level at which damage or mal-operation may occur (3600 volts or below), the operator immediately initiates a loss of voltage signal to the emergency buses by tripping the grid feeder breakers which automatically starts and loads the diesel generators with the auto-matically sequenced Class IE loads.
-- The degraded voltage sensing relay circuits are provided with ESF signal contacts such that at any time there is a degraded voltage alarm coin-cident with an ESF signal, the diesel generators will automatically start and power the Class IE safety loads.
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Safety Evaluation 4 l
CONCLUSION The staff has concluded, based upon the above considerations and theIlicensees connitment to implement the subject procedures prior to restart from the 1985/1986 outage, that:
(1) The licensee revised procedure OP-3140, provides technically acceptable operator actions during degraded grid voltage conditions without a LOCA to assure protection of Class 1E electrical systems and equipment.
(2) There is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.
Date: Itarch 31, 1986 Principal Contribution: Carl H. Woodard l
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