NRC Generic Letter 1991-009: Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies for the Reactor Protection SystemML031140136 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/27/1991 |
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From: |
Partlow J Office of Nuclear Reactor Regulation |
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To: |
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References |
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GL-91-009, NUDOCS 9106260172 |
Download: ML031140136 (6) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
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Category:NRC Generic Letter
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(Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal NRC Generic Letter 1983-111999-06-24024 June 1999 NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis ML0823509351999-06-0303 June 1999 Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal ML0311101371999-06-0303 June 1999 Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates NRC Generic Letter 1999-011999-05-0303 May 1999 NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities NRC Generic Letter 1998-011999-01-14014 January 1999 NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants ML0311101601998-08-0303 August 1998 Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data NRC Generic Letter 1998-041998-07-14014 July 1998 NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i NRC Generic Letter 1998-031998-06-22022 June 1998 NRC Generic Letter 1998-003; NMSS Licensees and Certificate Holders Year 2000 Readiness Programs NRC Generic Letter 1998-021998-05-28028 May 1998 NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition NRC Generic Letter 1997-061997-12-30030 December 1997 NRC Generic Letter 1997-006: Degradation of Steam Generator Internals NRC Generic Letter 1997-051997-12-17017 December 1997 NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques NRC Generic Letter 1996-061997-11-13013 November 1997 NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions ML0312007011997-10-0808 October 1997 Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions NRC Generic Letter 1997-041997-09-30030 September 1997 NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules NRC Generic Letter 1997-031997-07-0909 July 1997 NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees NRC Generic Letter 1997-021997-05-15015 May 1997 NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report NRC Generic Letter 1995-061997-01-31031 January 1997 NRC Generic Letter 1995-006: Changes in Operator Licensing Program NRC Generic Letter 1996-081996-12-15015 December 1996 NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators NRC Generic Letter 1996-051996-09-18018 September 1996 NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves NRC Generic Letter 1996-041996-06-26026 June 1996 NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks NRC Generic Letter 1995-091996-04-0505 April 1996 NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials NRC Generic Letter 1996-021996-02-13013 February 1996 NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat NRC Generic Letter 1996-031996-01-31031 January 1996 NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits NRC Generic Letter 1989-101996-01-24024 January 1996 NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors NRC Generic Letter 1996-011996-01-10010 January 1996 NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits NRC Generic Letter 1995-101995-12-15015 December 1995 NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation ML0310701501995-10-31031 October 1995 Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval NRC Generic Letter 1993-031995-10-20020 October 1995 NRC Generic Letter 1993-003: Verification of Plant Records NRC Generic Letter 1995-071995-08-17017 August 1995 NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves NRC Generic Letter 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes NRC Generic Letter 1995-041995-04-28028 April 1995 NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues NRC Generic Letter 1995-021995-04-26026 April 1995 NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59 NRC Generic Letter 1995-011995-01-26026 January 1995 NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities ML0312004431994-09-0202 September 1994 Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data NRC Generic Letter 1994-031994-07-25025 July 1994 NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors NRC Generic Letter 1994-021994-07-11011 July 1994 NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors NRC Generic Letter 1994-011994-05-31031 May 1994 NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators NRC Generic Letter 1993-081993-12-29029 December 1993 NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits NRC Generic Letter 1993-071993-12-28028 December 1993 NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans NRC Generic Letter 1993-061993-10-25025 October 1993 NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas. NRC Generic Letter 1993-051993-09-27027 September 1993 NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation NRC Generic Letter 1993-041993-06-21021 June 1993 NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) NRC Generic Letter 1993-021993-03-23023 March 1993 NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication NRC Generic Letter 1993-011993-03-0303 March 1993 NRC Generic Letter 1993-001: Emergency Response Data System Test Program 2023-08-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
m y WASHINGTON. D. C.20555
- June 27, 1991 TO: All HOLDERS OF OPERATING LICENSES FOR BOILING-WATER REACTORS
SUBJECT: MODIFICATION OF SURVEILLANCE INTERVAL FOR THE ELECTRICAL PROTECTIVE
ASSEMBLIES IN POWER SUPPLIES FOR.THE REACTOR PROTECTION SYSTEM
(Generic Letter 91-Q2)
.This generic letter provides guidance for requesting a license amendment to modify the surveillance interval for electrical protective assemblies (EPAs)
used in power supplies for the reactor protection system (RPS). The current standard technical specifications (STS) for boiling-water reactors (BWRs)
- require the licensee to perform channel functional tests of EPAs at a 6-month interval. The modification of EPA test interval provided by this generic letter is to change the TS to state that the test shall be performed each time the plant is in cold shutdown for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the test was performed in the previous 6 months.
In a proposal on December 15, 1988, for Nine Mile Point Nuclear Station (NMP),
Unit 2, the Niagara Mohawk Power Corporation provided a Justification that this TS change benefits plant safety. During the recent review of this TS change for Dresden Nuclear Power Station, Units 2 and 3, the U.S. Nuclear Regulatory Commission (NRC) staff noted that this change from the guidance of the BWR STS
had been implemented in the TS issued with 9 of the last 14 BWR operating licenses. The staff concludes that the TS-change applies generical-ly for...BWRs....
its a line-item TS improvement. The enclosure provides guidance for preparing a license amendment request to implement this line-item TS improvement.
Licensees are encouraged to propose TS changes for BWR facilities that are consistent with the guidance provided in the enclosure. The NRC project manager for the facility will review amendment requests conforming to this guidance. Please contact the NRC project manager or the contact identified below if you have questions on this matter.
This letter does not require any licensee to propose changes to its plant TS.
Therefore, any action taken in response to the guidance'provided in this generic letter is voluntary and is not a backfit under 10 CFR 50.109.
Sincerely, ames . Partlow ssociate Director for Projects Office of Nuclear Reactor Regulation Enclosure: As stated 77i/A _S
Contact: Tom Dunning, NRR/OTSB
(301) 492-1189
9106260172 am DK aIorZo ScP0c0 3 t
Generic Letter 91-09
-- Enclosure MODIFICATION OF THE SURVEILLANCE INTERVAL REQUIREMENTS FOR
ELECTRICAL PROTECTION ASSEMBLIES IN REACTOR'PROTECTION POWER-SUPPLIES
Introduction This enclosure provides guidance for preparing a request for a license amendment to modify the technical specifications (TS) surveillance interval requirements for the electrical protection assemblies (EPAs) used in power supplies for the reactor protection system (RPS) for boiling-water reactors (BWRs). This change reduces the possibility for inadvertent reactor trips caused by testing of EPAs during power operation.
Discussion To protect RPS equipment from abnormal operating voltage or frequency produced by RPS motor generator (MG) sets or an alternate power supply, EPAs-will trip a breaker between the MG sets and the RPS. TS 4.8.4.4 in the standard technical specifications (STS) for BWRs addresses 'the surveillance requirements for EPAs.
This TS specifies that licensees perform a channel functional test every
6 months.
To functionally test an EPA channel, the licensee transfers the power for the RPS from the associated MG set to the alternate power supply. Because the transfer of RPS power involves a dead-bus transfer, power ismomentarily interrupted which causes a half scram or group isolation. Alternatively, the licensee could perform tests without a bus transfer, but this procedure also results in a momentary interruption of power to the RPS when each EPA channel is tripped during the channel functional test. At many BWR plants, licensees have encountered problems with the reset of the half-trip conditions, following testing of EPAs during power operation, resulting in inadvertent scrams and group isolations that challenge safety systems.
An alternative to testing the EPAs every 6 months during power operation has been to test them each time the plant is in cold shutdown for more than
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if this test has not been performed within the previous 6 months.
This alternative eliminates the need to test the EPAs during power operation and, thereby, reduces the possibility of inadvertent challenges to the protec- tion systems. However, this alternative retains testing within the existing
6-month interval when the unit isshut down for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during an operating cycle.
If the licensee does not encounter a cold shutdown of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more during a fuel cycle, the effect of not testing EPAs during this interval is a small risk to safety. This alternative benefits safety by reducing the possibility for inadvertent trips and challenges to safety systems. The staff concludes that the benefit to safety of reducing the frequency of testing during power operation more than offsets the risk to safety from relaxing the surveillance requirement to test EPAs during power operation.
The following guidance provides an acceptable alternative inthe format of the current BWR STS for these surveillance requirements:
k Generic Letter 91-09
- 2 - Enclosure
4.8.4.4 The above specified RPS electrical shall be determined OPERABLE: power monitoring assemblies a. By performance of a CHANNEL FUNCTIONAL
plant is in COLD SHUTDOWN for a period of TEST each time the unless performed in the previous 6 months. more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Summary The modification of the surveillance interval tests for EPAs in accordance with this guidancefor performing channel functional to test EPAs during power operation. The will eliminate the requirement elimination of this testing during power operation will reduce the possibility for challenges to safety systems. The implementation inadvertent trips and improvement will produce a net benefit for of this line-item TS
safety.
- - *^s LIST OF RECENTLY ISSUED GENERIC LETTERS
Generi c
- Date of Letter No. Subject Issuance Issued To
91-08 REMOVAL OF COMPONENT LISTS 05/06/91 ALL HOLDERS OF OLs FROM TECHNICAL SPECIFICATIONS OR CPs FOR NUCLEAR
POWER REACTORS
91-07 GI-23 "REACTOR COOLANT PUMP 05/02/91 ALL POWER REACTOR
SEAL FAILURES" AND ITS LICENSEES AND
POTENTIAL IMPACT ON STATION HOLDERS OF CPs BLACKOUT
91-06 RESOLUTION OF GENERIC ISSUE 04/29/91 ALL HOLDERS OF OLs A-30, *ADEQUACY OF SAFETY-
RELATED DC POWER SUPPLIED,"
PURSUANT TO 10 CFR 50.54(f)
91-05 LICENSEE COMMERCIAL-GRADE 04/09/91 ALL HOLDERS OF OLs PROCUREMENT AND DEDICATION AND CPs FOR NUCLEAR
PROGRAMS POWER REACTORS
91-04 CHANGES IN TECHNICAL SPECIFI- 04/02/9l ALL HOLDERS OF OLs CATION SURVEILLANCE INTERVALS OR CPs FOR NUCLEAR
TO ACCOMMODATE A 24-MONTH FUEL POWER REACTORS
CYCLE
91-03 REPORTING OF SAFEGUARDS 03/06/91 ALL HOLDERS OF OLs EVENTS OR CPs FOR NUCLEAR'
POWER REACTORS AND
ALL OTHER LICENSED
ACTIVITIES INVOLVING
A FORMULA QUANTITY
OF SPECIAL NUCLEAR
MATERIAL (SNM)
91-02 REPORTING MISHAPS INVOLVING 12/28/90 ALL OPERATORS OF
LLW FORMS PREPARED FOR LOW-LEVEL RADIO-
DISPOSAL ACTIVE WASTE (LLW)
DISPOSAL SITES,
WASTE PROCESSORS,
& ALL HOLDERS OF
LICENSES FOR NUCLEAR
FUELS, NUCLEAR
MATERIALS & NUCLEAR
POWER REACTORS
91-01 REMOVAL OF THE SCHEDULE FOR 01/04/91 ALL HOLDERS OF OLs THE WITHDRAWAL OF REACTOR OR CPs FOR NUCLEAR
VESSEL MATERIAL SPECIMENS POWER PLANTS
FROM TECHNICAL SPECIFICATIONS
90-09 ALTERNATIVE REQUIREMENTS FOR 12/11/90 ALL LIGHT-WATER
SNUBBER VISUAL INSPECTION REACTOR LICENSEES
INTERVALS AND CORRECTIVE AND APPLICANTS
ACTIONS
June 27, 1991 TO: All HOLDERS OF OPERATING LICENSES FOR BOILING-WATER REACTORS
SUBJECT: MODIFICATION OF SURVEILLANCE INTERVAL FOR THE ELECTRICAL PROTECTIVE
ASSEMBLIES IN POWER SUPPLIES FOR THE REACTOR PROTECTION SYSTEM
(Generic Letter 91-09)
This generic letter provides guidance for requesting a license amendment to modify the surveillance interval for electrical protective assemblies (EPAs)
used in power supplies for the reactor protection system (RPS). The current standard technical specifications (STS) for boiling-water reactors (BWRs)
require the licensee to perform channel functional tests of EPAs at a 6-month interval. The modification of EPA test interval provided by this generic letter is to change the TS to state that the test shall be performed each time the plant is in cold shutdown for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless the test was performed in the previous 6 months.
In a proposal on December 15, 1988, for Nine Mile Point Nuclear Station (NMP),
Unit 2, the Niagara Mohawk Power Corporation provided a justification that this TS change benefits plant safety. During the recent review of this TS change for Dresden Nuclear Power Station, Units 2 and 3, the U.S. Nuclear Regulatory Commission (NRC) staff noted that this change from the guidance of the BWR STS
had been implemented in the TS issued with 9 of the last 14 BWR operating licenses. The staff concludes that the TS change applies generically for BWRs as a line-item TS improvement. The enclosure provides guidance for preparing a license amendment request to implement this line-item TS improvement.
Licensees are encouraged to propose TS changes for BWR facilities that are consistent with the guidance provided in the enclosure. The NRC project manager for the facility will review amendment requests conforming to this guidance. Please contact the NRC project manager or the contact identified below if you have questions on this matter.
This letter does not require any licensee to propose changes to its plant TS.
Therefore, any action taken in response to the guidance provided in this generic letter is voluntary and is not a backfit under 10 CFR 50.109.
Sincerely, James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure: As stated cc: See attached Distribution:
See attached *See previous concurrence.
OTS Ebb Tech Editor OTSB:DOEA C:OTSB:DQ 1 C:OGCB:DOEA a TGD t :tgd JMain* FMReinha w / IGrime CHBerlinger J (
06/le291 06/12/91 06/12-/91 '06/It /91 06//e/91 7 Concurrence continued on next page.
_,Holders of Operating Licenses for BWRs -2 -
cc w/enclosures:
J. Sniezek F. Miraglia Division Directors, NRR
Associate Directors, NRR
Project Directors, NRR
Regional Administrators J. Conran, CRGR
C. Berlinger, DOEA
S. Treby, OGC
Distribution: (GL 91-09)
PDR (N49-e DOEA R/F
OTSB R/F
Central Files TGDunning
_-- 1 NOTE: This generic letter was reviewed during the CRGR meeting of June 11,
1991, and the CRGR had no objection to it being issued. A copy of the generic letter, the memorandum distributing it to project managers, and the generic safety evaluation report were provided to the CRGR staff. Subsequently, J. Conran, CRGR staff, noted that all CRGR comments have been addressed by the final versions of these documents.
Contact: Tom Dunning, NRR/OTSB /V,_,.' A. 7otf aA"-e0 ,C
(301) 492-1189 ? ~,~
OFFICIAL RECORD COPY A; C-/T AFv
_1 ,nt{
CONCURRENCE CONTINUED-" 91 07- a I M60_7__
, 2 X_*_z rr77 Co.l C- 1vs-f VUlT:'KN7 AUY: RKKr W1u el I JGPartlow \,
06/1 7191 /91 06V/91
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