Text

Proposed Tech Specs Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3%
	ML20117J339
Person / Time
Site:	Sequoyah
Issue date:	08/28/1996
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20117J336	List: ML20117J334; ML20117J339; ML20117J361;
References
	NUDOCS 9609100285
	Download: ML20117J339 (23)
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ENCLOSURE 1 i PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 l l

DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-96-07) l LIST OF AFFECTED PAGES '

Unit 1 3/4 4-3 l 3/4 4-4 i

3/4 7-1 l

3/4 7-3 Unit 2 l

l 3/4 4-6 3/4 4-7 3/4 7-1 l 3/4 7-3 l

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9609100285 960828 PDR ADOCK 05000327 P PDR .

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REACTOR COOLANT SYSTEM hk 3/4.4.2 SAFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2 A minimum of one pressu 'zer a lift setting of 2485 PSIG

code safety valve shall be OPERABLE # with R10q APPLICABILITY: MODES 4 and 5 3% .

ACTION:

With no pressurizer code safety valve OPERABLE, immedietely suspend all opera-tions involving positive reactivity changes and place an OPERABLE RHR loop into operation in the shutdown cooling mode. I SURVEILLANCE REQUIREMENTS '

4.4.2 l No additional by Specification 4.0.5.Surveillance Requirements other than those required '

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The lift setting pre'ssure shall correspond to ambient conditions of the valve of nominal operating temperature and pressure.

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A safety valve is not required OPERABLE provided at least one safety valve is R10E removed from the pressurizer and the associated RCS breech is not covered by a pressure retaining membrane. !

SEQUOYAH - UNIT 1 3/4 4-3 i Amendment No. 104 ;

March 9, 1989 -

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REACTOR COOLANT SYSTEM

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3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING _.

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SAFETY VALVES - OPERATING 1

i LIMITING CONDITION FOR OPERATION l

l 3.4.3.1 l setting of All2485 pressurizer PSIG + code

safety valves shall be OPERABLE with a lift

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APPLICABILITY: MODES 1, 2 and 3. 3%

ACTION:

With one i pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l SURVEILLANCE REQUIREMENTS i 4.4.3.1 FP l Specification 4.0.5.No additional Surveillance Requirements other than those required by

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The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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SEQUOYAH - UNIT 1 ' 3/4 4-4 september 17, 1980 V

l 3/4.7 PLANT SYSTEMS l

3/4.7.1 TURBINE CYCLE l SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 Main . steam safety valves (MSSVs) shall be OPERABLE with lift settings as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2 and 3.*

ACTION:

a. With one or more MSSVs inoperable, operation may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1. The provisions of Specification 3.0.4 are not applicable.

b. With the requirements of ACTION a., not met or with one or more steam

generators with less than two MSSVs OPERABLE be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . -

l -- SURVEILLANCE RE0VIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5. -

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With the reactor trip system breakers in the closed position. l April 4, 1995 3/4 7-1 Amendment No. 114, 196 SEQUOYAH UNIT 1

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TABLE 3.7-2 l R260 b STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING ff B

N0ZZLE SIZE

' Loop 2 Loop 4 l.000 1 Loon 3 5 3%

Z 1-1-522 1-1-517 1-1-512 1-1-527 1064 psig 16 sq. in.

1-1-523 1-1-518 1-1-513 1-1-528 1077 psig 16 sq. in.

1-1-524 1-1-519 1-1-514 1-1-529 1090 psig 16 sq. in.

1-1-525 1-1-520 1-1-515 1-1-530 1103psis 16 sq. in.

1-1-526 1-1-521 1-1-516 1-1-531 1117 psig 16 sq. in.

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The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure. ,

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REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES - SHUTDOWN -

l LIMITING CONDITION FOR OPERATION i

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3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE # with a l lift setting of 2485 PSIG t

lR93 i

APPLICABILITY: MODES 4 and 5. 3%

ACTION: ,

With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE residual heat removal loop into operation in the shutdown cooling mode, i

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SURVEILLANCE REQUIREMENTS l

4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5. -

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e "The lif t setting pressure shall correspond to ' ambient conditions of ' the valve at nominal operating temperature and pressure.

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A safety valve is not required OPERABLE provided at least one safety valve is R93 removed from the pressurizer and the associated RCS breech is not covered by a i

pressure retaining membrane, t

SEQUOYAH - UNIT 2 3/4 4-6 Amendment No. 93 March 9. 1989 l

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REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3.1 All pressuriz ode safety valves shall be OPERABLE with a lift setting of 2485 PSIG

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l SURVEILLANCE REQUIREMENTS -

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4.4.3.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

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"The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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SEQUOYAH - UNIT 2 3/4 4-7 I

l 3/4.7 PLANT SYSTEMS 3/4.7.I TURBINE CYCLE ;

SAFETY VALVES LIMITING CONDITION FOR OPERATION l

R187 '

3.7.1.1 Main steam safety valves (MSSVs) shall be OPERABLE with lift settings as specified in Table 3.7-2.

APPLICABILITY: MODES 1, 2 and 3*.

ACTION:

a. With one or more MSSVs inoperable, operation may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1. The provisions of Specification 3.0.4 are not applicable.

1 With the requirements of ACTION a., not met or with one or more steam b.

generators with less than two MSSVs OPERABLE be in at least HOT i STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE0VIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5. "

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With the reactor trip system breakers in the closed position. April 4, 1995 !

3/4 7-1 Amendment No. 104, 107 SEQUOYAH - UNIT 2 i

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TABLE 3.7-2 la187 E STEAM LINE SAFETY VALVES PER LOOP 8

h VALVE NUMBER LIFTSETTING(i@* N0ZZLE SIZE h . Loon 1 LooD 2 Loon 3 Loon 4 2-1-522 2-1-517 2-1-512 2-1-527 1064 psig 16 sq. in. '

2-1-523 2-1-518 2-1-513 2-1-528 1077 psig 16 sq. in.

2-1-524 2-1-519 2-1-514' 2-1-529 1090 psig 16 sq. in.

2-1-525 2-1-520 2-1-515 2-1-530 1103 psig 16 sq. in.

2-1-526 2-1-521 2-1-516 2-1-531 1117 psig 16 sq. in.

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The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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I ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE l SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SON-TS-96-07)

DESCRIPTION AND JUSTIFICATION FOR 1 PRESSURIZER SAFETY VALVE (PSV)

AND MAIN STEAM SAFETY VALVE (MSSV)

SETPOINT TOLERANCE INCREASE l

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Descriotion of Chanae TVA proposes to modify the Sequoyah Nuclear Plant (SON) Units 1 and 2 technical specifications (TSs) to revise the appropriate sections to increase the setpoint tolerance for the PSV and the MSSV from plus or minus one percent to plus or minus ,

three percent. These parameters are contained in TS 3.4.2, TS 3.4.3.1, and l Table 3.7-2. Additionally, the sentence "Following testing, lift settings shall be within 1%." will be added to Surveillance Requirement (SR) 4.4.2, 4.4.3.1, and 4.7.1.1. ,

l Reason for Channe TVA is requesting a revision to TS 3.4.2, TS 3.4.3.1, and Tcble 3.7-2 to relax the l setpoint tolerance for the PSVs and the MSSVs. Based on industry and SON i experience, the plus or minus one percent tolerance is not sufficient to accommodate valve setpoint drift over an entire fuel cycle. Industry standards (American National Standards Institute /American Society of Mechanical Engineers OM-1) recognize that

plus or minus three percent is an acceptable criteria. TVA wishes to take advantage of this industry supported relaxation.

Justification for Chanaes l The applicable plant transients and accidents evaluated in the SON Updated Final Safety Analysis Report (UFSAR) were reviewed to determine the effect of PSV and MSSV setpoint tolerance relaxation. The safety evaluation of safety valve setpoint tolerance relaxation is contained in Enclosure 5 of this letter. The positive increase i from one percent to three percent of the setpoint tolerance does not challenge the overpressure protection capability of the PSVs or MSSVs. This is supported by the reanalysis of the bounding overpressure events. Additionally, the negative tolerance change was evaluated for an increased mass release from the MSSVs to the l atmosphere. The evaluation confirmed that all radiological consequence analyses, which model a MSSV actuation, remain within tha requirements of 10 CFR 100 with the increased steam release. Additionally, the PSVs and the MSSVs will be returned to plus or minus one percent after testing to allow for setpoint drift; therefore, l providing a high level of confidence that the valves will remain within the specified setpoint tolerance.

Environmental Imoact Evaluation The proposed change does not involve an unreviewed environmental question because j operation of SON Units 1 and 2 in accordance with this change would not:

l 1. Result in a significant increase in any adverse environmentalimpact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmentalimpact appraisals, or decisions of the Atomic Safety and Licensing I

Board.

2. Result in a significant change in effluents or power levels.

3. Result in matters not previously reviewed in the licensing basis for SON that may

have a significant environmentalimpact.

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4 4 l ENCLOSURE 3 i

PROPOSED TECHNICAL SPECIFICATION CHANGE 1

SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 l

DOCKET NOS. 50-327 AND 50-328 l (TVA. SON-TS-96-07) l DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION FOR PRESSURIZER SAFETY VALVE (PSV)

AND 1

MAIN STEAM SAFETY VALVE (MSSV)

! SETPOINT TOLERANCE INCREASE 1

9 Significant Hazards Evaluation TVA has evaluated the proposed technical specification (TS) change and has determined that it does not represent a significant hazards consideration based on l criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant (SON) in accordance with the proposed amendment will not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated. l The evaluation contained in Enclosure 5 discusses the consequences of this change as it pertains to the accidents previously analyzed. The positive increase of the setpoint tolerance, from one percent to three percent, of the PSV and the l MSSV does not challenge the design limits of the installed systems. This I conclusion is demonstrated by means of the reanalysis of the bounding overpressure events. The negative tolerance for the MSSVs, from minus one percent to minus three percent, will result in an increase in mass discharged through these valves. The increase was evaluated and the analysis indicated that the dose release remained within the limits required by 10 CFR 100. Based on the results of this review, there is no increase in the probability of a previously l evaluated accident or a significant increase in the consequences of an accident

! previously evaluated.

2. Create the possibility of a new or different kind of accident from any previously analyzed.

The proposed TS change willincrease the setpoint tolerance for the PSVs and the MSSVs. This change does not involve an equipment addition or change in the method the plant is operated. Therefore, the possibility of a new or different kind of accident from any previously analyzed is not created.

3. Involve a significant reduction in a margin of safety.

The proposed change is a change in the lift setpoint tolerance of the existing valves. The analysis demonstrates that the design limits are not exceeded nor are l the dose release limits exceeded due to this increase in setpoint tolerance.

Additionally, the valves will be returned to the original tolerance of plus or minus one percent. This will ensure that the maximum margin is retained; therefore, the margin of safety has not been reduced by this change.

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ENCLOSURE 4 1 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE i SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 l (TVA-SON-TS-96-07) l REVISED TS PAGES

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S e REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE with a lR108 lift setting of 2485 PSIG i 3%.* l APPLICABILITY: MODES 4 and 5 ACTION:

With no pressurizer code safety valve OPERABLE, immediately suspend all opera-tions involving positive reactivity changes and place an OPERABLE RHR loop into operation in the shutdown cooling mode.

SURVEILLANCE REQUIREMENTS 4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5. Following testing, lift settings shall be within i 1%. l

The lift setting pressure shall correspond to ambient conditions of the valve of nominal operating temperature and pressure.

A safety valve is not required OPERABLE provided at least one safety valve is R108 removed from the pressurizer and the associated RCS breech is not covered by a pressure retaining membrane.

SEQUOYAH - UNIT 1 3/4 4-3 Amendment No. 104,

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REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING SAFETY VALVES - OPERATING LIMITING CONDITION FOR OPERATION 3.4.3.1 All pressurizer code safety valves shall be OPERABLE with a lift lFP setting of 2485 PSIG i 3%.* l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3.1 No additional Surveillance Requirements other than those required by lFP Specification 4.0.5. Following testing, lift settings shall be within 1%. l l

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The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure. ,

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SEQUOYAH - UNIT 1 3/4 4-4 Amendment No.

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i 3/4.7 PLANT SYSTEMS i

I 3/4.7.1 TUFBINE CYCLE SAFETY VALVES l

l LIMITING CONDITION FOR OPERATION 3.7.1.1 Main steam safety valves (MSSVs) shall be OPERABLE with lift settings as specified in Table 3.7-2.

! APPLICABILITY: MODES 1, 2 and 3.* R200 l

ACTION:

a. With one or more MSSVs inoperable, operation may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is j reduced per Table 3.7-1. The provisions of Specification 3.0.4 are l not applicable. 1 l

b. With the requirments of ACTION a., not met or with one or more steam generators with less than two MSSVs OPERABLE be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional' Surveillance Requirements other than those required by l Specification 4.0.5. Following testing, list settings shall be within i 1%. l 'l l

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With the reactor trip system breakers in the closed position. lR200 I

SEQUOYAH - UNIT 1 3/4 7-1 Amendment No. 114, 196, l

J

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER LOOP lR200 ,

VALVE NUMBER LIFT SETTING (+ 3%)* NOZZLE SIZE l Loon 1 Loon 2 Loon 3 Loop 4 1-1-522 1-1-517 1-1-512 1-1-527 1064 psig 16 sq. in.

1-1-523 1-1-518 1-1-513 1-1-528 1077 psig 16 sq. in.

1-1-524 1-1-519 1-1-514 1-1-529 1090 psig 16 sq. in.

1-1-525 1-1-520 1-1-515 1-1-530 1103 psig 16 sq. in.

1-1-526 1-1-521 1-1-516 1-1-531 1117 psig 16 sq. in.

The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

SEQUOYAH - UNIT 1 3/4 7-3 Amendment No. 196,

. --. _ - . . . . - - . __. - - . = -. _____ - _ _- - -. _. - - - . __ .__ __

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REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES - SHUTDOWN 1

l LIMITING CONDITION FOR OPERATION I 3.4.2 A minimum of one pressurizer code safety valve shall be OPERABLE # with a lR93 lift setting of 2485 PSIG i 3%,* l APPLICABILITY: MODES 4 and 5. '

l ACTION: ;

l With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE residual heat removal loop into operation in the shutdown cooling mode. I i

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SURVEILLANCE REQUIREMENTS 4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5. Following testing, lift settings shall be within i 1%. l !

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The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

A safety valve is not required OPERABLE provided at least one safety valve is removed from the pressurizer and the associated RCS breech is not covered by a R93 pressure retaining membrane, l

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I SEQUOYAH - UNIT 2 3/4 4-6 Amendment No. 93,

i ,

e REACTOR COOLANT SYSTEM 3/4.4.3 SAFETY AND RELIEF VALVES - OPERATING l

l l SAFETY VALVES - OPERATING l

t

! LIMITING CONDITION FOR OPERATION l 3.4.3.1 All pressurizer code safety valves shall be OPERABLE with a lift

! setting of 2485 PSIG i 3%.* l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.3.1 No additional Surveillance Requirements other than those required by Specification 4.0.5. Following testing, lift settings shall be within i 1%. l l l

The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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SEQUOYAH - UNIT 2 3/4 4-7 Amendment No.

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s o 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION t

3.7.1.1 Main steam safety valves (MSSVs) shall be OPERABLE with lift settings R187 as specified in Table 3.7-2.

APPLICABILITY: Modes 1, 2 and 3*.

ACTION:

a. With one or more MSSVs inoperable, operatien may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Setpoint trip is reduced per Table 3.7-1. The provisions of Specification 3.0.4 are not applicable.

b. With the requirements of Action a., not met or with one or more steam i generators with less than two MSSVs OPERABLE be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by l l

, Specification 4.0.5. Following testing, lift settings shall be within i 1%. l l

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'With the reactor trip system breakers in the closed position.

( R187-l l

j SEQUOYAH - UNIT 2 3/4 7-1 Amendment No. 104, 187, ,

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TABLE 3.7-2 lR187 STEAM LINE SAFETY VALVES PER LOOP VALVE NUMBER LIFT SETTING (+3%)* NOZZLE SIZE l Loco 1 Loon 2 Loco 3 Looo 4 2-1-522 2-1-517 2-1-512 2-1-527 1064 psig 16 sq. in. )

I 2-1-523 21-518 2-1-513 2-1-528 1077 psig 16 sq. in.

2-1-524 2-1-519 2-1-514 2-1-529 1090 psig 16 sq. in.21-525 2-1-520 21-515 2-1-530 1103 psig 16 sq. in. l 2-1-526 2-1-521 2-1-516 2-1-531 1117 psig 16 sq. in. )

1 I *The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

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SEQUOYAH - UNIT 2 3/4 7-3 Amendment No. 187,

. o ENCLOSURE 5 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE I'

SEQUOYAH NUCLEAR PLANT (SON) UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328-(TVA-SON-TS-96-07) l FRAMATOME TECHNOLOGIES INCORPORATED SAFETY EVALUATION OF SAFETY VALVE SETPOINT TOLERANCE RELAXATION t

i 77-1257369-01 l

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ML20117J339

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