ML20077A720

Proposed Tech Specs Reflecting Removal of Accelarated Testing & Special Reporting Requirements for EDGs & Revising SR 4.8.1.1.3 Bases Section 3/4.8.1 Paragraph 6 to Add GL 94-01

ML20077A720
Person / Time
Site:	Comanche Peak
Issue date:	11/18/1994
From:	TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20077A710	List: ML20077A707 ML20077A720
References
GL-94-01, GL-94-1, NUDOCS 9411250166
Download: ML20077A720 (24)

Text

ATTACHHENT 3 TO TXX 94310 AFFECTED TECHNICAL SPECIFICATION PAGES (NUREG 1468) i 1

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9411250166 941118 PDR ADOCK 05000445 .

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Attachment 3 to TXX-94310 Page.1"of 6 i

IfiQil LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I

l 5ECTION EME 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating................................................ -3/4 8-1 1 TABLE 4.8-1 6 ..N.@.ys Q ,,,,,,,,,,, ;g ;;g

• Shutdown................................................. 3/4 8-10 3/4.8.2 D.C. SOURCES 0perating................................................ (

3/4 8-11 i TABLE 4.8-2 8ATTERY SURVEILLANCE REQUIREMENTS..................... 3/4 8-13 Shutdown................................................. 3/4 8-14 3/4.8.3 ONSITE POWER DISTRIBUTION Operating................................................ 3/4 8-15 Shutdown................................................. 3/4 8-17 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices....................................... 3/4 8-18 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................... 3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................... 3/4 9-2 3/4.9.3 DECAY TINE............................................... 3/4 9-3 3/4.9.4 CONTAIHMENT BUILDING PENETRATIONS........................ 3/4 9-4 3/4.9.5 C0MUNICATIONS........................................... 3/4 9-5 3/4.9.6 REFUELING MACHINE........................................ 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS.................. 3/4 9-7 j 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION

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High Water Leve1......................................... 3/4 9-8 Low Water Leve1.......................................... 3/4 9-9 l l 3/4.9.9 WATER LEVEL - REACTOR VESSEL l

Fuel Assemblies..........................................

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3/4 9-10 Control Rods............................................. 3/4 9-11 3/4.9.10 WATER LEVEL - IRRADIATED FUEL STORAGE.................... 3/4 9-12 COMANCHE PEAK - UNITS 1 AND 2 ix I

- . . ___ _ _ __ _ _ _ _ _____ _ _ __ __-_-_-_.-- ___________ _J

Attachment 3 to TXX-94310 i Mage 2 of 6 l ELECTRICAL p0WER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

f. With two of the above required diesel generators inoperable, demon-strate the OPERABILITY of two offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1.la. within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next G hours and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore at least two diesel generators to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from time of initial loss or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE0VIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System shall be:

a. Determined OPERABLE at least once per 7 days by verifying correct

- breaker alignments, indicated power availability, and

b. Demonstrated OPERABLE at least once per 18 months during shutdown by '

transferring (manually and automatically) the 6.9 kV safeguards bus power supply from the preferred offsite source to the alternate offsite source.

4.8.1.1.2 Egch diesel generator shall je demonstrated OPERABLE:

a. D Icc r r.c N h t c fr h c 4 ccified in ieble '." [on a STAGGERED TEST BASIS by:

1) Verifying the fuel level in the day fuel tank,

2) Verifying the fuel level in the fuel storage tank,

3) Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day fuel tank,

4) Verifying the diesel starts from ambient condition and acceler-ates to at least 441 rpm in less than or equal to 10 seconds.*# l

• All planned diesel engine starts for the purpose of this surveillance may be preceded by a prelube period in accordance with vendor recommendations.

1. The diesel generator start time (10 seconds) shall be verified at least once per 184 days. All other engine starts for performance of this surveillance, may use a diesel generator start involving gradual acceleration to synchronous speed as recommended by the manufacturer.

i COMANCHE PEAK - UNITS 1 & 2 3/4 8-3 Unit 1 - Amendment No. 29  ;

Unit 2 - Amendment No.15  ;

1 1

. Attachment 3 to TXX-94310

F8P 3IEb'RICALPOWERSYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a) Barring device engaged, or b). Maintenance Lockout Mode.

g. At least once per 13 years or after any modifications which could affect diesel generator interdependence by starting both diesel generators simultaneously,* during shutdown, and verifying that both diesel generators accelerate to at least 441 rps (58.8 Hz) in less than or equal to 10 seconds; and

h. At least once per 10 years by:

1) Pumping out each fuel oil storage tank, removing the accumulated sediment and cleaning the tank using a sodium hypochlorite solution or equivalent, and

2) Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code, when tested pursuant to Specification 4.0.5.

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i preceded by a prelube period in accordance with vendor recommendations. l COMANCHE PEAX - UNITS 1 AND 2 3/4 8-S 1

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Attachment 3 to TXX-94310

- Page 5.of 6 ELECTRICAL POWER SYSTEMS A.C. SOURCES SHUTDOWN l

LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be .

OPERABLE:

a. One circuit between the offsite transmission network and the Onsite Class IE Distribution System, and

b. One diesel generator with:

1) Day fuel tank containing a minimum volume of 1440 gallons of fuel,

2) A fuel storage system containing a minimum volume of 86,000 gallons of fuel, and

3) A fual transfer pump.

APPLICABILITY: MODES S and 6.

ACTION:

4 With less than the above minimum required A.C. electrical power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reactivity changes, movement of irradiated fuel, or crane operation with loads over the fuel storage pool, and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System through a greater than or equal to 2.98 square inch vent. In addition, when in MODE 5 with the reactor coolant loops not filled, or in MODE 6 with the water level less than 23 feet above the reactor vessel flange, inmediately initiate corrective action to restore the required sources to OPERABLE status as soon as possible.

4 SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the requirements of Spec _ifications ,

. 71.1Q4.8.1.1.2 (except for Specification 4.8.1.1.2a.5))f in: ;.;.;.(."

uL COMANCHE PEAX - UNITS 1 AND 2 3/4 8-10

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-Attachment 3 to TXX-94310 Page 6 of 6 ELECTRICAL POWER SYSTEMS l BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)

The Fuel Storage System consists of the fuel oil storage tank and is equivalent to the ANSI N195-1976 definition for supply tank.

The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Sup- l plies," March 10, 1971; 1.108, " Periodic Testing Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977; and 1.137, " Fuel-Oil Systems for Standby Diesel Generators," January 1978, Gen-eric Letter 84-15, en fGeneric Letter 83-26, " Clarification of Surveillance I

Requirements for Diesel Fuel Impurity Level Tests.", d 6eme LcHer 14-o[l "

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j l The Surveillance Requirement for demonstrating the OPERABILITY of the l l

station batteries are based on the recommendations of Regulatory Guide 1.129, i " Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear  ;

Power Plants," Revision 1, February 1978, Regulatory Guide 1.32, " Criteria for '

l Safety Related Electric Power Systems for Nuclear Power Plants," Revision 2, J February 1977, and IEEE STD 450-1980, "IEEE Recommended Practice for Mainte-nance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations."

The operational requirement to energize the instrument busses from their associated inverters connected to its associated 0.C. bus is satisfied only when the inverter's output is from the regulated portion of the inverter and not from

the unregulated bypass source via the internal static switch.

4 Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values, and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates, and compares the battery capacity at that time with the rated capacity.  ;

Table 4.8-2 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float Voltage, and specific  ;

gravity. The limits for the designated pilot cells float voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal l limits for each connected cell for float voltage and specific gravity, greater ,

than 2.13 volts and not more than 0.020 below the manufacturer's full charge l specific gravity with an average specific gravity of all the connected cells not 1 more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery. ,

COMANCHE PEAK - UNITS 1 AND 2 8 3/4 8-2

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ENCLOSURE 1 TO TXX-94310 GENERIC LETTER 94 01, " REMOVAL OF ACCELERATED TESTING AND SPECIAL REPORTING REQUIREMENTS FOR EHERGENCY DIESEL GENERATORS", MAY 31, 1994 l

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ALL HOLDERS OF OPERATING LICENSES FOR NUCLEAR POWER REACTORS

SUBJECT:

REMOVAL OF ACCELERATED TESTING AND SPECIAL REPORTING REQUI FOR EMERGENCY DIESEL GENERATORS (GENERIC LETTER 94-01) l The U.S. Nuclear Regulatory Commission (NRC) is issuing this generic letter to advise licensees that they may request a license amendment to remove accelerated testing and special reporting requirements for emergency diesel generators (EDGs) from plant technical specifications (TS). The NRC developed i

this line-item TS improvement in response to the Commission decision on SECY-93-044, " Resolution of Generic Safety Issue 8-56, ' Diesel Generator Reliability'." Enclosure 1 is the guidance on preparing the amendment request and Enclosure 2 is the model TS for this change.

In Option 4 of SECY-93-044, the staff recommended that licensees adopt the accelerated testing provisions of f e improved Standard Technical Specifications with an option to r .ocate accelerated testing requirements for EOGs from the IS to the maintenr, into effect. However, after ft, ther a program after the maintenance rule goes consideration, the staff has concluded that it is not necessary to await the effective date of the maintenance rule to remove the associated TS requirements nor is it necessary to relocate accelerated testing requirements to the maintenance program. Licensees may now implement the provisions of the maintenance rule for EDGs, including the applicable regulatory guidance which will provide a program to assure EDG performance.

Therefore, the requirements for accelerated testing of individual EDGs would no longer exist.

Licensees may request the removal of the TS provisions for accelerated testing and special reporting requirements for EDGs at this time. However, when requesting this license amendment, licensees must commit to implement within 90 days of the issuance of the license amendment a maintenance program for monitoring and maintaining EDG performance consistent with the provisions of Section 50.65 of Title 10 of the Code of Federal Reculations (10 CFR 50.65),

" Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," and the guidance (as applicable to EDGs) of Regulatory Guide (RG) 1.160, " Monitoring the Effectiveness of Maintenance at Nuclear Power Plants."

The NRC staff developed RG 1.160 to provide guidance for complying with the provisions of 10 CFR 50.65.

Some licensees do not have TS requirements for accelerated testing of EDGs and reporting each EDG failure to the NRC, but may have made a docketed commitment to such actions. In such cases, licensees may request relief from a docketed commitment for accelerated testing and special reporting requirements for 9405190384 i

4 4

Generic Letter 94-01 May 31, 1994 1

l EDGs.

Such requests should be made on the basis of implementation of the l provisions of the maintenance rule and associated regulatory guidance (as applicable to EDGs) within 90 days of NRC granting relief from a docketed I commitment.

i l

Licensees that plan to adopt this line-item TS improvement are encouraged to propose TS changes that are consistent with the enclosed guidance in Enclosures 1 and 2. Licensees that plan to request relief from a docketed commitment to accelerated testing of EDGs and special reporting of EDG failures in are encouraged Enclosure 1. to propose such requests consistent with the guidance Licensee action to propose TS changes or relief from a docketed commitment under the guidance of this generic letter is voluntary. Therefore, such action is not a backfit under the provisions of 10 CFR 50.109. As such, the staff did not perform a backfit analysis.

The voluntary information collections contained in this request are covered by the Office June of Management and Budget clearance number 3150-0011, which expires 30, 1994 The public reporting burden for this voluntary collection of information is estimated to average 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of in forma t ion .

Send commeats regarding this burden estimate or any other aspect of this voluntary collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch (MNBB-7714), U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and to the Desk Officer, Office of Information and Regulatory Affairs, NE08-3019, (3150-0011), Office of Management and Budget, Washington, D.C. 20503.

Compliance with the following request for information is voluntary. The information generic would assist NRC in evaluating the cost of complying with this letter:

(1) the licensee staff time and costs to prepare the amendment request (2) an estimate of the long-term costs or savings accruing from this IS change

Generic Letter 94-01 May 31, 1994 If you have any questions about this matter, please contact one of the technical contacts listed below or the appropriate Office of Nuclear Reactor Regulation project manager.

Sincerely, p 7 .-f Luis A. Reyes Acting Associate Director for Projects Office of Nuclear Reactor Regulation

Enclosures:

1. Guidance on Preparing the Amendment Request

2. Model TS for Change

3. List of Recently Issued NRC Generic letters Technical contacts: Om Chopra, NRR (301) 504-3265 Tom Dunning, NRR (301) 504-1189

Enclosure 1 GUIDANCE FOR IMPLEMENTING A LINE-ITEM TECHNICAL SPECIFICATION (TS)

IMPROVEMENT TO REMOVE ACCELERATED TESTING AND SPECIAL REPORTING REQUIREMENTS FOR EMERGENCY DIESEL GENERATORS (EDGs)

FROM PLANT TECHNICAL SPECIFICATIONS OR FROM 00CKETED COMMITMENTS

Background

As part of the resolution of Generic Safety Issue (GSI) 8-56, " Diesel Generator Reliability," the staff of the U.S. Nuclear Regulatory Commission (NRC) recommended Option 4 in SECY-93-044, " Resolution of Generic Safety Issue B-56, ' Diesel Generator Reliability'." The Commission approved Option 4 on March 25, 1993. In Option 4, the NRC staff recommended (in part) that licensees be allowed to voluntarily adopt the accelerated testing provisions of the improved Standard fechnical Specifications; and upon a determination that the maintenance program conforms to the applicable guidance, the accelerated testing requirements for the EDGs could be relocated from the TS to the maintenance program when the maintenance rule goes into effect in 1996.

However, after further consideration, the staff has concluded that it is not necessary to await the effective date of the maintenance rule to remove the associated TS requirements nor is it necessary to relocate accelerated testing requirements to the maintenance program. Licensees may now implement the provisions of the maintenance rule for EDGs, including the applicable regulatory guidance, which will provide a program to assure EOG performance.

The elements of this program will include the performance of a detailed root cause analysis of individual EDG failures, effective corrective actions taken in response to individual EOG failures, and implementation of EDG preventive maintenance consistent with the maintenance rule.

The staff has concluded that licensees may also propose TS changes to remove special reporting requirements for EOGs from their plant TS. Licensees may also raquest relief from a docketed commitment for accelerated testing of EOGs and reporting each EDG failure to the NRC. Licensees would continue to comply with the provisions of 10 CFR 50.72 and 50.73 to notify NRC and report EDG failures. With this TS change or NRC relief from a docketed commitment to such actions, requirements for accelerated testing of EDGs would no longer exist.

The staff approval of this option would be contingent upon a commitment to implement, within 90 days of a license amendment, or NRC granting relief from a docketed commitment, a maintenance program for monitoring and maintaining EDG performance in accordance with the provisions of 10 CFR 50.65,

" Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," and the guidance contained in Regulatory Guide (RG) 1.160,

" Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." The fulfillment of this commitment need not necessarily result in a new or separate EDG maintenance program but rather could be traplemented by modifi-cation of existing maintenance program requirements that include EDGs. )

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1 l

9 Discussion The NRC staff developed RG 1.160 to provide flexibility for licensees to structure their maintenance program based on the risk significance of the structures, systems, and components that are within the scope of the maintenance rule. This guide endorses a Nuclear Utility Management and Resources Council (NUMARC) guideline' which gives methods acceptable to the NRC staff for complying with the provisions of the maintenance rule (10 CFR 50.65).

During the public comment period for this generic letter, the staff met with the Advisory Committee for Reactor Safeguards (ACRS). As a consequence of continuing ACRS concerns on the use of trigger values, included in a NUMARC guideline,2 the NRC staff will modify RG 1.160 by removing the language on the use of trigger values for monitoring EDG performance. However, the staff intends to retain in RG 1.160 the discussion on NRC's expectations that licensees would (1) establish performance criteria for both emergency diesel generator reliability and unavailability, under paragraph (a)(2) of the maintenance rule, (2) perform appropriate root cause determination and corrective action following a single maintenance-preventable failure, and (3) establish goals and monitor subsequent EDG performance under paragraph (a)(1) of the maintenance rule if any performance criterion is not met or a second EDG maintenance-preventable failure occurs.

In addition to the focus on paragraphs (a)(1) and (2) of the maintenance rule as addressed in the NRC's expectations on implementing the guidance of RG 1.160, paragraph (a)(3) of the maintenance rule must also be met and requires (in part) that licensees make adjustments where necessary to ensure that the objective of preventing failures through maintenance is appropriately balanced against the objective of minimizing unavailability due to monitoring or preventive maintenance.

Therefore, a commitment to implement the maintenance rule consistent with the guidance of RG 1.160 as applicable for EOGs is a commitment to (1) implement the endorsed NUMARC guideline, 93-01, with the exception of the reference to NUMARC 87-00 on the use of trigger values and (2) fulfill the NRC staff expectations discussed in RG 1.160. Should licensees wish to propose an alternative to implementing the guidance of RG 1.160, to demonstrate compliance with the maintenance rule for EDGs, the NRC staff will consider such proposals.

The NRC staff finds that a commitment to implement a maintenance program for monitoring and maintaining EDG performance in accordance with the provisions of the maintenance rule and consistent with the guidance of RG 1.160 would provide a basis for the staff to approve a licensee request to remove the

'NUMARC 93-01, " Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," May 1993.

2 Appendix D of NUMARC 87-00, Revision 1, " Guidelines and Technical Cases for NUMARC Initiatives Addressing Station Blackout at LWRs," August 1991.

accelerated testing and special reporting requirements for EDGs from their plant TS. This commitment would also provide the basis for the staff to approve requests for relief from a docketed commitment to accelerated testing of EDGs and reporting each EDG failure. Licensees must commit to implementing within 90 days of the issuance of the license amendment or commitment relief the provisions of IC CFR 50.65 and guidance of RG 1.160 for EDGs when requesting the removal of the EDG accelerated testing and special reporting requirements from their plant TS or docketed commitment. The elimination of accelerated testing requirements for EDGs closes the matter of triggers and testing for " problem diesels."

Enclosure 2 includes model EDG technical specifications which address these TS changes.

e Enclosure 2 MODEL STANDARD TECHNICAL SPECIFICATIONS FOR REMOVING ACCELERATED TESTING AND SPECIAL REPORTING REQUIREMENTS FOR EDGs Revisions to TS 4.8.l.l.2 (Changes are shown in bold typeface.)

4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1) through 7) no change.

(Removes the reference to TS Table 4. 8.1.1.2-1 for the test schedule.)

Revisions to Table 4.8.1.1.2-1 (Changes are shown in bold typeface.)

TABLE 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE (Not used)

(Removes accelerated testing requirements for EDG's which were based on the number of failures in the last 20 and 100 valid tests.)

Revisions to TS 4.8.1.1.3. "Recorts" (Changes are shown in bold typeface.)

4.8.1.1.3 Reports (Not used)

(10 CFR 50.72 and 50 73 address the remaining regulatory requirements for licensees to notify NRC and report individual EDG failures.)

l

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ENCLOSURE 2 TO TXX 94310 SAFETY EVALUATIONS, INSPECTION REQUIREMENTS FOR TDI, DIESEL GENERATORS (TAC N0, M85325)

MARCH 17, 1994 PAGES 1, 2 SER 1. 6, 7, 9, 10 AND 11

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SUSJEC-SAFET! EVALUATICN. INSPECTION REQUIREMENTS FOR TRAN

[NC. :IESEL GENE 0ATORS (TAC NO. M85325)

~5e su:mit:ec cansamerica :r :csals on Celaval Novemcer (TDI) diesel generators Owners' Grouc (Owners' Gr u:)

E,alua:t:n) anc :ecemoer 7 30,1992 (Reference 1 in the enclosed Safe y 1993 (Reference 2), recommending removal of licenstng ccnct: ions imposed as part of a technical resolution to address .

c:ncerns regarcing the reliability of the TOI emergency diesel generators ~

(ECGS) following the crankshaft failure at Shoreham in August 1983. The tecnnical resolution involved implementation of Phase I and Phase II programs 9 as identified in NUREG-I216 (Reference 3). The Phase I program focused on the resolutton of known engine component problems -that had potential generic imolications, wntle the Phase II program focused on the design review of a

'arge set of imoortant engine components to ensure their adequacy from a tanuf acturing standooint, as well as operational performance. At that time, the staff c:ncluded that these components merited special emphasis in the area

f loao restrictions and/or maintenance and surveillance. The 16 major ccmoonents

/ i incer bloc <s, wnien were identified included connecting rods, crankshaf ts.

cylinder heads, piston skirts, and turbochargers.

load restrictions were addressed in the plant Technical Specifications, Engine license conditions, engine coerating procedures and operator training, as accroortate, for five of these components. The most critical periodic maintenance / surveillance actions for these components were incorporated as license concittons.

On the casts of substantial operational data and insoection results the Owners' Group provided information in References 2 and 3 to demonstrate : hat

ne scecial concerns of NUREG-1216 are no longer warranted.

The Owners' Grcue statec that the T0! EDGs should be treated on a par with other EDGs within : 9e nuclear industry and subjected to the same standard regulations, without *he scecial reautrements of NUREG-1216. In addition, the Owners' Group statec that this action will improve availability of the engines for service, esceciall

! Ouring outages, while maintaining current reliability levels.

The NRCa staff comDieted reviewand of the itsoperational consultants dataatandPacific Northwest inspection results containec Laboratories 'n (P the accitten, Cwners' Grouc submittal reports relative to the individual components. 'n ex ert: regarcirg incecendent ooinions were obtained from three leading diesel engi e these inscection reoutrements,

l

, :1f I Cn :ne pas 1s of its review, the staff has concluded that there is acecuate sust.f 4 cation for removing the present component-based licensing condittons.

Yne mef's evaluation of the Cwners' Group's suomittal reports is in the g:3:nec safet/ evaluation (SE).

.t s .e :e2 at tne attacnec SE be referenced by affected licensees 'n Orc:asals for :nanges to f acility licenses to tne extent specif f ed and uncer tne itmitations delineated in the licensee submittals and the associateo NRC evaluation. The evaluation defines the basis for the approval of the reports and is applicable to the eight Owners' Group licensees: Texas Utilities for I

Comanene Peak; Entergy Coerations for Grand Gulf; Ouke Power for Catawba; Carolina Power for Shearon Harris; Georgia Power for Vogtle; Clevelano l j

Electric Illuminating for Perry; Grand Gulf Uttlities for River Send; and Tennessee Valley Authority for Bellefonta. i In accordance with procedures established in NUREG-0390, the TOI Owners' Group  !

is requested to publish coproved versions of the Owners Group reports as generic topical reports within three months of receipt of this staff approval, l j

The accepted version should incorporate this approval letter and the enclosed ,

evaluation between the title page and the abstract. The approved version -

shall include an -A (designating approved) following the report identification symool, i

The staff does not intend to repeat its review of the approved matters described in the approved generic topical reports when the reports appear as references in license applications except to assure that the material l' presented is applicable to the specific plant involved. The staff's approval applies only to the matters described in the reports.

Should the staff's criteria or regulations change so that the staff's conclusions as to the acceptability of the reports are invalidated, the j i

Owners' Group and/or the licensees referencing the reports will be expected to i revise and resubmit their respective documentation, or submit justification for the continued effective applicability of the reports without revisions of l their respective documentation. {

l Sincerely, f6bt.~ 6f. <S J

James A. Norberg, Chief Mechanical Engineering Branch Division of Engineering i

Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation

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E :.13 !'_ : < :s0 : E '. : 15:.: !7:ii ? iw!:GENCY JI!$!L iiNE;.2*:;5 l

st:aC';:!O iv :Niaw!3 M A :Elaval. :NC. l Y:CCC'"N l 1

.c ; e .!"s. any .:1? ties :r:ered vesel genera::rs fr:s Transa e, : .i

M avai, :,c. i t;I) ':r *nstallati:n at nuclear slants in the Uniteo 5:stes. I

~ a es: Of t ese eagines is :ec:me Ocerational in nuclear service were . ::e l it San Cnofra Unt: 1 in !977. dewever, nuclear plant perating excer'ecce  !

ein **

• per ency ::asel ,ar.erators (!!Gs) rematnad very limited unt?' -

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rec:erational test :r: grams ere started at Shorenas and Grano Galf .ni: '. l I

• ,e early 1980s.

. 1 C:ncerns aceut the reli teility of l arge-bore, medium-soned diesel genert::rs truf actureo my TOI for a:olication at :cmestt: nuclear olants ere first

r: oted my a cranssnaft failure at Shorenas in August 1983. However, a :r:t: i

attern f

efletencies in critical engine ccmconents suosecuently :eca::e evident at Shorenam and at other nuclear and non-nuclear fac11ittes tacicyta;

• 01 diesel generators. These deficiencies stemed frem inadequactes in l design, manufacture, and quality assurance / quality control by TOI. . .- '

In response to these problems, 11 (now 8) U.S. nuclear utility cwners' i

formed a T0! Diesel Generator CMners' Group to address operational and regulatory issues relative to diesel generator sets used for standby e?arge :/

cwor. On March 2,1984, the Owners' Group submitted a proposed pregets ('*

:

Owners' Group Program Plan') to the NRC that was intended to provide an n-deoth assessment of the adequacy of the respective utilities' TOI engi es ::

erform their safety-related function through a combination of design revie.s. ,

uality revaltdations, engine tests, and component inspections.

The Qwners' Group program addressed three major elements concerning tne anuf acture. Inspection, and operation of TOI diesel engines:

s!) Shase I: Resolution of known generic engine component proolims t: se se as a basis for licensing plants during the period before c:moietten :?

3hase II of the Owners' Group program.

,2) Phase !!: A Design Review / Quality Revalidation (OR/QR), of a 'arge a:

Of imoortant engine components to ensure that their design and

?anufacture, including specifications, quality control and ;ual' /

assurance, and operattenal surveillance and maintenance, are 1:a:21:e (3) itoanded engine tests and inspections as needed to support P ase 1*:

! :regrates.

f arolina 7:wer ind t.tght Co. (Shearon Harris), Cleveland Elect-'c-lIluminating Co. (3erry), Ouxe Power Co. (Catawea), Georgta Pcwer : L

. N tie). Lif States Gttl.t es (River Sand), intergy Coerations, :-c.

Grano Lif ; nits 1 12), 7A jal;ef:nta), Texas Uttlities (C: anc e

eat).

5

:::ses M ase tv s ;arer'  : esel anagerent :r:gra:s in 1:ey :/ : e ,.. .

-antanancaisurver M isca recutrements.

n : e :asts of ine subs'.antial operattonal experience of the T0! cgs i::.-it:ed s ce ;H! 49d tne inspectt:n results of the (OG c:mponents. : e

. + s' : :. as : : viced tiformation in its sucmittal reports Of Nc.e :er M. 332. nac ece-:er 7.1393 (References 2 and 3) to demonstrate inat ; e s: ectal c:ncerns :( WREG 1216 are no longer warranted. The Owners' 3r:uo 1.

ec: rtended removing the license condittens related to EOG component us: actions involvtrg tenedewns and surveillance requirements.

The Owners' Group has analyzed the need for engine overhauls in ac:ortance witn the current CR/QR recutrements. Their analysis and conclusions are :ase:

n an understanding of the historical concerns for each comoonent affe::ac :f 19e overnaul and the results of extensive inspections performed by the i teensees .no maxe uo the T0! Cwners' Group. The informatten in its su:m t:a' re: orts incluces c:moonent description c:moonent identiff ettion numcer :er

9e CR/QR accenoix II. #7Peventive Maintenance (PM) Task Descriotton.' :9e "anufacturer's replacement /overnaul recomendations, the number of engine

'ours run Oetween insoections or cumulative engine nours, numeer of engJne starts, inspection findings, and the percentage of all components in'sirvice covered by the inspections. The results of the inspections como!1ed by the Owners' Group in its submittsi reports (References 2 and 3) tndicate tnat res-teardowns have shown little or no wear on internal engine cotto nents.

However, with continuing operation, it is possible that probleu c:Jid Oc:yr 4

witn specific components unich could require inspection or overnaul :f affected components. The Owners' Group is proposing that such actt:ns-:e determined on a case-by-case basis, and that inspections or overnauls :e performed so that engine reliability and availability are maximized. The Owners' Group contends that the primary purpose of EDG 10-year teardown inspections is to document the condition of the specific components, not to replace components, since most components being inspected show little or no

< ear. However, as a matter of good-maintenance practice, these comconents

, 4re generally replaced after a teardown inspection, regardless of co.1citt:n.

These teardowns can result in reassembly errors or entry of foreign 9atarials 4

resulting in increased wear or dt.:reased engine reliability.

?*e Cwners' Group believes that an overhaul will be needed during the Ie :#

t'ese engines as they are currently operated. However, due to ne I m:ec mumber of run hours and the availability of periods to perform major :sarea,ns

se licensees need the flexibtitty to determine when an overhaul is recuirec and how an overhaul is conducted.

751 Cwners' Group ::ntends that some of the early concerns with (CG c: :: e":

aare cau:ed by the deleterious effects of the fast starts and I:ad! g :f ??i to nuclear service. The Owners' Group notes that the life expectancy :! ost i

sagine c:moonents in c:.:eretti servica, which are not subject to 'ist :: W :

s f ar greater than the estimated life of EOG components in nuclear service cased on early data, all ticansees nave the luiharity to delete f ast-start and loading rewe? e-~

n the casts of Generic Letter (GL) 34-15, and are comitted to 001 7 13.

?

- .eser. s:me I cersees ave act taten tats steo f:e a nu.tcer of eas:ns.

1  : -s:. -any eng1.%s save c:nte: 1 sf sta9s ant n will ,et allow a si:w surt.

a ecessary c3anges in soca c:nte 1 s/ stems are carrentlj bateg t.?clemanuc.

t::-:. ::9e of : e *0I licensees vant ;3 c:nsolidata all csanges f:e a

i-: .. i ac , cal s:ect f tcatten (*S) to !assan : .e t pact :n .na  :, see I i: ; + WC . orc:ac resuittsg fr:i a 'S change recuest. The suff s

.crently Oreparing a 31. Acdressing the requirements for accelerated test g

f e ergency diesels. Most licensees are waiting for this Gl. to :e tss.ec l

efure requesting a enange to their TSs anien would include a request ':r a

eitt::n of tne f ast surts. Cnce tne slew start :otton is tra'e e uc arc accelerated testing is eliminated, engines at nuclear plants will te aceratec s ntlarly to those in c:mercial service, aad the excected life of c:m:enants i

?n engines at nuclear plants snould coroare favoraoly with c:mercul eng!ne 1

-conents. The data from engines in nuclear service which have imclementse

ae s!:w-start cotton succorts this contention. Since the manufacturer's ec: rendations for camercial coeratton of T0!/EDG components prior :s

<ernaul indtcate that there are suestantial safety margins available.

Accrocriate enanges can be mace in M/S recutrements based on realistic est: mates of cemconent life excectancy, and flextbtlity can be acnieved in : e ~

frequency of perforntng teardown inspections. -

No C*wners' Group, in its submittal reports, has also discussed the need for flextollity in scheduling teardown inspections from the sta'ndootnt of shutd:wa risk management (SRN). According to the Owners' Group, the 'available

. indows' of outage time of sufficient length to allow engine teardewns anct:r overnauls are being shortened because of SRM requirements. The 'availacle window' during which a diesel can be removed free service for maintenance depends on a nuacer of factors, including plant design, availability of alternate power sources, fuel handling schemes, and other operational, l

• aintenance, or inspection requirements. These factors cause the 'available .

aindow' to vary from outage to outage. Typically, the 'available window

• is l

etween 10 and 21 days; however, SRM programs have compressed this ' window' :f as mucn as 20%. As a result of this shortening of *available windows,' all

1 ants need riaximum flexibility in scheduling EOG maintenance activit:es

. e., schedule major diesel worlt during times when longer

• windows' are available without impacting overall outage length). Time-directed aarcowns/ overhauls do not allow this flexibility. The Cwners' Group is

rcoosing a generic diesel management program which combines credicttve atntenance, surveillance, and inspection. The Owners' Group contenos :nat

< *ith this program, considerable flex 1bility can be achieved in the fettenc!

Of :erforming teardowns and/or overnauls without sacr 1ficing engine eliaotlity, i i

S:tcal ccmconents that are inspected or replaced or coth during an ergre l

,ernaul are turbochargers, main bearing caps / studs, cylinder clocxs, '

~re".'99 reds, earirgs/busnings, cylinder heads, cush rods, lower cyl'ncer l

'iner seals, base assemolies, crank snaf ts, cylinder liners, otstens, rings.

Sel .nf ecticn tubing, and roc ~ter arm caoscrews/ drive studs. Proolems at:9 )

'asse c mponents resulting frem the intrusive inspections could certaint f l

isit or oreclude the engine's acceptacle ;ower output. Disas:emely :f esi l

?cenents can result in tne acctdantal intecduction of dirt and :t er #: s' ^ !

atertals that may narm the engine. In addition, these components are

__m..J- a m. m 3

e factuse s:ee:n c survelliances,'ns:ec' :ns .ere c: sed 3y ,ggiag.:. ..  ;

iasare t34t ic:ectacle engine c:nd!!':ns .ere :eirg .4,nta ngg, ;., 1 9s;ection results snculd 90t !!entify unacca:taole fMetags, l

' e '.ners' Group shculd have an alternative 1tesel -anagement r:grii

- i t ents tnat are n dged Oy :re regulat:ry sta'r to :e eas: a:*, t c: 4:.a:'f ef fective c:moared to c.rrent iteense recutrewnts , l a: tatnirg c1esel reliability.  ;

~'e underly'ng source or tecnnical basis for the orocosed requiat:cf

nange snould to p.stified by authertttes and espertt se ecuti ts at

.nica determined the current regulatory requirements.

is discussed in the following paragraphs, all ff ve criteria have :een sat:sfied. The current T01 engine reliability was found to be equal ts :r

etter than the industry average.

4 In the certed between January 1990 and

ecemcer !392, the median reliacility of 70! diesels was found to :s 0.31C5.

~ hts is acout 14 cetter than the nuclear industry average. and ell a:cve WC's nignest goal of 0.375.

5:ecifte surveillances/ inspections were imposed by NRC regulattens to ensuri

nat accootabl e T0[ engine conditions were being maintained. A revies o't t e 3cerational dataease and the inspection results for the key c moonents, as discussed in Appendix A, show no unacceptable findings. In fact. ost inJoactions did not uncover any signs of wear or degradation that need t: :e addressed.

NRC-soonsored research (Reference 4) has indicated the potentially egattve consequences of intrusive inspections on components and engine reli40tlity is a result of current practices. In a study of failures related to aging, a failure curve, sometimes called the ' bathtub

• curve, correlates the enange n failure d

rate with age. The beginning segment of the curve represents a '. ear-in portion, with a higher fat' ure rate associated with many pieces of new equ?cment. Once the machinery is broken in, the f ailure rate is at its 1:.est and reiains constant for a period of time. As the machinery wears and reatnet the end of its lifetime, the failure rate increases. The challenge is to determine the time scale for these regions for each place of equi: cent. n Pe casts of these studies, it is generally believed that the diesel engine's eliability is considerably lower during the

• wear-in* period, and s:me engines may be on the lower end of the acceptable range of reliactiit/. : r:

tne '. ear-in* period of operation.

5:me of the early concerns with EOG componenti were due to the :eleter':us af fects of fast start and loading of EOGs in nuclear service. C:mecnent 't "cectancy in comercial TOI engines which are not subject to f ast starts i 1r greater than life expectancy for T01 engine components in nud ar are:e Alt 3cugn the f ast start requirements have been relaxed on the basis of R i -

15. act, all licensees have implemented the changes in the EDG c:-t-d n i-

'o :ermit slow starts. All memeers of the Owners' Group are comitted t:

implementing these changes in the near future. The staff is alsa 1:0ms'";

• he issues related to accelersted testing in a generic letter to 08 issuto inert 1 /. Na the s'.ww start :stten has teen t plownted and Icce'irl i:

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' ut* 7 45 :etn ei ninated. aciste stav' e eag'as :: erat':n .i:1 re

' :ta'y *aten that :f engines a ::.g ere'll service arc t.e er:ectic :: ::re.: !

't #:e ~]! ea91nes in nuctene service 5.0u'd ::,mcire 'tvera:! f ,iti l

t ea:'ai tagtne ::moonent le. *5e cata ' :9 eag'nes :n auct ear tere:e l

.r :n 1.e  : 'e enteo tile sitw-start :M t:.1 s.;;crts t9 s ::-:ta: ':- t e< e :p *. e anuf acturer's rec: r'ancat':es f:e ::xeret al : east :n :'

l

':! E:G e:moonents :efore evernaul 'ncicates tnat tnere are s:.cstant ai :a'et, '

argins availaole for most ::mconents in nuclear service. **e staff ::-:.rt ~

aita tne Owners' Group recomendation tnat ')y ecmotning redict;de aintenance, surveillance, and inscactt:ns, as in the :r: x sec ;a !" : 6:ei anagement orogram, c:nsideraole flextollity can be acnteved in : e ' e:.enef i Sf :erforming engine taardowns and/or ovnenauls .nthout sacrificing eagt e celtability.

• 5e Owners' Group c:ntends that tne 'available windcws' Of cutage tt e of saff tetsnt lengtn to allow engine teardowns and/or overnauls are ceiag mortened due to SRM recuirements. As a result of tnis snortening :f vallaole windows, all plants need maximum flexibiltty in seneaulirg ECG aintenance activities. The adoption of a crootetive maintenance 3r gess f:e '

!:Gs as arcoosed, in lieu of the current time-directed teardown /overn.aul" requirements would give the licenses this flexibility without 'tocarcizing engine reliability.

The Owners' Group has requested the removal of inspection requirements f : t the license conditions. The Owners' Group proposes to continue accroortate inspections; however, scope, inspection schedules, and especially De i cunt of intrusive inspections involving disassembly would be changed to maxtmize

!OG availability and reliability. Inspections would be planned to rescend to monitoring and trending results and where other maintenance activittes taxe the c:moonent accessib's, such as in response to f ailures of nearby ::moonents

r where Sonitoring is indicating an end of component life conditions. The Owners' Group will cont,inue appropriate inspections, especially those not involving engine disassembly. Inspections will be defined and irchend as

art of a well-managed engine program currently under preparation. [169ents f Orrect engine management have been reported previously to the NRC and iadustry (References 8 and 9). Xey features of an EOG management gr: gram.

1:r. notable to the staff (see Appendix C of this safety evaluation) nave :een

iscussed and provided to the Owners' Grouo. The Owners' Group agrees t'at eacn mem0er would adopt the group's proposed jeneric management Or: gram.

esolution, or mitigating actions, and that ail actions are intanced i: :e acceotable to the manufacturer.

" ally, the underlying source or technical basis for the proposed regulat:r/ l

. 13 is equal in excertise to that whico o s etoonsttle for -e::? ea r g

e :ar ent regulatory requirements. The T0! Cwners' Group, altn :.::crt '":-

• e tauf act.rer, as instemental in crectring the technical basis f:r e

riginal regulatory concittens n NUREG-1216.

l. CVERALL CONCL'JSICNS l i

e staf f, <1tn assistance fr:s its c:nsultants and rec:gnizac : 7sf r: i ex:erts, c:ncluded tnat tne regulatory require ents on 70! engines 1/ :e l l

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,:: : :ered it :vs :"e. 'n's ::ne!;st:n :s :asec :n a ev.aw 3f ~ ,

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-el'iot! :f :4:a :# "a *:: e"qtres. :ne Owners Ir:uo as:ec: : s :' l 3 ist :everal ,, ears, anc Me :stnion :/ experts .no nave ex:er'e:e , e l

as ;a r: ::eri: :n :! 'ar;e ctesel engines. 'he staff :et eves ra: : e :: '

. e '. :.:. <e 19/ :ver :.ners gr:uo, tust accress : a .s  :.e 1 - t i :t eecs #:r ':s 1:ect! c engtae to teto tne reltaot t':f 'te::e  !

i::t::1:le.

3r:.o, Inc ?:s

.1:n a :graea eatin reliaoility of 0.390ci, Pe "; :eers- l

-ct o:aal : ners, seem to fully uncerstand tne -a'nteaacce  :

etes :f nts eagine. ~5e staf f furtner :elieves that uere 's saf": t-- '

-8:r ation tn taa :=ners 3 coup sucmittal reports to c:nctace . 5: *:: ye'

eration at author?:eo loads is accootable under normal SRC regulat:ry

<erstgnt procedures for iCGs. The staff and its cansultants, in tneir -ev i.

/ :na T01 submittal recorts and the operattenal datae.se, d!d not .nr.:<er a f ,

ew c:ncerns or issues. I"cividual reports from rec:gnized exper:s eacerse l any of the 701 engine management cracttees, inspections, or precautions. e

!.ners' 3roup intenos to : c:r: orate ost of the inscections ano :recautt:ns

' , ne current M/S requirements in its generic diesel 9anagement :r:get, c:

iocre riately succlement t?ese inscoctions with alternate conct:::n oni :r --

rececures. All temcers of the Cwners' Group are c:mitted to :le ent, at s

tesel management program.

Me key features of a saintenance progrart which the st3ff finds accectable tre

elineated in Appendix C of this safety evaluation. The staff has reviewed

ne :reliminary version of the diesel management program. which the 0.ners' Group is crocosing in lieu of the current N/$ requirements. The staf' '":s the principal elements of this program acceptable. The croposed maintaaarce

r: gram is in confomance with the requirements in Regulatory Guide !.;ic.

Monitoring the Effectiveness of Maintenance at Nuclear Power Plants. ' f ate:

June 1993, which endorses NUMARC 93-01 dated May 1993, *:ndustry Guide f:e w

onitoring the Effectiveness of Maintenance at Nuclear Pswer Plants.'

a ce:rdingly, the staff has concluded that the license conditions related t:

ne certodie M/S program (see Appendix 0 of this safety evaluat:en) for

ertain components (see Appendix E of this safety evaluatton) antch ere

ted on the licensees based on the recomendations in NUREG-1216 ce ae*oved at this time. Therefore, the detailed steos of the preventive M/S Or grams will not be subject to NRC staff review and approval. However. Me s:1f f telieves that future revisions of the M/S program nould te sue:ect :

"e arovisions of 10 CFR 10.59 (Code of Federal ReaulatMns) in ne. :/ r e

ortance of the M/S orogram in ensuring the operaotlity and reli 40'? / :#

"a engines. The staff will require that the owners of eacn olant :: 91: ::

"a current M/S program in the interim period preceding Se 190lemen:1r:n '

Pe gectric diesel management orogram currently under development, n j

ass:c t at':n and agreemerit <ith the tant.facturer. The transit?cs

• 9 Pe

.r est M/S Or: gram to the generic diesel management program c:uld :e 1::: c1::?ec .acar Pe Or:vtstens of 10 CFR 50.59. The TS recuirements :-,

swo;ecting the ciesel to an ins:ection in accordance w th procedures .es:i-!:

'n c:njunction with its ?.truf teturtr's ree:mriendattons for the class :#

sianoby service would continue to remain in effect, similar to tne *S ,

• utre*ents :n utner (CG nanufacturers.

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