ML20127B819

Safety Evaluation Supporting Amend 105 to License NPF-29

ML20127B819
Person / Time
Site:	Grand Gulf
Issue date:	01/06/1993
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20127B818	List: ML20127B814 ML20127B819
References
NUDOCS 9301130140
Download: ML20127B819 (11)

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UNITED STATES 3

/ i NUCLEAR REGULATORY COMMISSION (kl{.Q,'/

W ASHINGTON. D.C. 205E4 s...

• SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.105 TO FACILITY OPERATING LICENSE NO NPF-29 ENTERGY OPERATIONS. INC.. ET AL.

GRAND GULF NUCLEAR STATION. UNIT 1 DOCKET NO. 50-416

1.0 INTRODUCTION

By letter dated July 29, 1992, the licensee (Entergy Operations, Inc.)

submitted a request for changes to the Grand Gulf Nuclear Station, Unit 1 (GGNS) Technical Specifications (TS).

The proposed TS changes incorporate reliability-based improvements to instrumentation Action Statements and surveillance test intervals based on NRC-approved Licensing Topical Reports previously submitted by the Boiling Water Reactor Owners Group (BWROG), of which Entergy Operations, Inc., is a member.

This safety evaluation verifies that the TS changes proposed by the licensee and their associated justifications are bounded by the analyses provided in the approved topical reports and that any plant-specific issues are adequately addressed.

2.0 EVALVAT1011 The licensee's proposed changes modify the following TS sections: (1) Section 3.3.4.2, End-of-Cycle Recirculation Pump Trip System Instrumentation; (2) Table 3.3.5-1 and Table 4.3.5.1-1, Reactor Core Isolation Cooling (RCIC)

System Actuation Instrumentation; (3) Section 3/4.3.6, Control Rod Block Instrumentation; (4) Table 3.3.7.1-1 and Table 4.3.7.1-1, Radiation Monitoring Instrumentation; (5) Table 3.3.8-1 and Table 4.3.8.1-1, Plant Syster.a Actuation Instrumentation; (6) Sections 4.4.2.1.1, 4.4.2.1.2, and 4.4.2.2.1, Roactor Coolant System; (7) Sections 4.5.3.1 and 4.5.3.2, Emergency Core Coc' O'} Systems (ECCSs); and (8) Modifications to related Bases.

Staff approval of plant-specific TS changes was conditional upon satisfactory resolution of two issues:

(1) The licensee must confirm that the generic analyses of the topical reports are applicable to the plant.

In the license amendment requests cited in References 16 and 19, the licensee confirmed that the generic analyses of References 4 through 9 apply to GGNS.

In addition, a review of the instrumentation logic configuration descriptions of GENE-770-06-1 (Reference 1) confirmed I

9301130140 930106 PDR ADOCK 05000416 P

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a.

that the technical bases presented in Reference 1 are applicable to GGNS.

GENE-770-06-2 (Reference 2) provided analyses of the RCIC instrumentation using fault tree end input data described in Reference 5 and using the BWR 5/6 model described in Case SA of Reference 6.

As described in the amendment request for ECCS instrumentation (Reference 19), Entergy Operations, Inc., confirmed that the ECCS generic model (which included the RCIC system) described in References 5 and 6 was applicable to GGNS.

It is therefore confirmed that the generic analyses of GENE-770-06-2 are applicable to GGNS.

(2) The licensee must confirm that any increase in instrument drift due to the extended surveillance test intervals (STis) is properly accounted for in the setpoint calculation methodology.

The instrumentation channel drift characteristics in question are considered when the TS trip setpoints are established.

The setpoint calculations for GGNS conservatively assume that the channel setpoint drift occurs without correction during the entire 18-month channel calibration interval.

Extension of the functional test intervals and associated calibrations, as proposed herein, will therefore have no effect on the instrumentation setpoint calculations.

The GGNS setpoint methodology thus continues to properly account for instrument drift.

A 15 change is proposed for TS Section 3/4.3.7.1, Radiation Monitoring Instrumentation, to extend the STis and the Allowed Outage Times (A0Ts) for the Containment and Drywell Ventilation Exhaust Radiation Monitor, the fuel Handling Area Ventilation Exhaust Radiation Monitor, and the fuel Handling Area Pool Sweep Exhaust Radiation Monitor.

These monitors are the same radiation monitors for the Isolation Actuation functions for which STI and A0T extensions were requested in Reference 19 and approved by the NRC in Reference 24.

The changes proposed in this amendment would increase the STI for functional tests from monthly to quarterly, their A0T from 1 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and their surveillance A0T from 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

These changes are wholly consistent with the proposed changes to primary containment isolation instrumentation and secondary containment isolation instrumentation STis and A0Ts approved by the NRC in Reference 24, and are needed to ensure that the specifications governing the same equipment are not in conflict.

Further justification for the extensions is described in Reference

19. Discussion of the applicability of the analysis to these proposed changes was transmitted to the NRC in the Response to Question 9 of Reference 23.

1

An additional change is requested to TS Section 4.5.3.1 to extend the Channel functional STI from 31 to 92 days and to provide a 6-hour surveillance A0T for the wide-range suppression pool water level instrumentation.

The wide-range suppression pool water level instrumentation uses the same trip units as the Suppression Pool Hakeup System (SPMS) instrumentation.

This amendment request proposes changing the Channel Functional STI and the surveillance A0T for the SPHS instrumentation in an identical fashion.

This change is therefore needed to ensure consistency among the specifications.

2.1 Ertd-of-Cycle Recirculation Pump Trio System Instrumentation The licensee has proposed modifications to the End-of-Cycle Recirculation Pump Trip System Instrumentation TS.

Under TS 3.3.4.2, the time limits for Action Statements b. and c.l. are increased from 1 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The time limit in footnote (a) for Table 3.3.4.2-1 is changed from 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These changes are consistent with the approved changes in Reference 1, and are therefore a:ceptable.

The proposed changes to TS Section 3/4.3.4.2 include an additional change on Tabl e 4.3.4.2.1-1, which is not reflected in the TS mark-ups provided in Reference 1.

This additional change consists of changing the calibration frequency required by footnote # from once per 31 days to once per 92 days.

This additional proposed change is justified by the analysis of Reference 1, since, as discussed in Section 3.2 of Referuce 1, the changes proposed are bounded by the analysis of Reference 4.

The scope of the analysis of Reference 4 included the evaluation of the effects of the extension of the required calibration intervals to 92 days; therefore, the extension of the surveillance interval required by footnote # to 92 days is bounded by these analyses and is acceptable.

2.2 Reactor Core Isolation Coolino System Actuation Instrumentation The licensee has proposed several modifications to the RCIC System Actuation Instrumentation TS.

In Table 3.3.5-1, footnote (a), the time limit is changed from 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Action Statement 50 is rewritten to state:

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels requirement:

a.

With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or declare the RCIC system inoperable, b.

With more than one channel inoperable, declare the RCIC system inoperable.

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4 4-The proposed changes to TS Table 3.3.5-1 modify the GGNS Action 50 to correspond to the BWR 6 Standard TS and Action 50 proposed in Reference 2 and accepted by the NRC via Reference 22.

The GGNS proposed Action 50 does differ from the Action 50 marked up in Reference 2 in that the GGNS Action 50 does not discuss the inoperability of a channel on a per trip system basis.

The GGNS 15 to which this Action requirement applies does not address the minimum number of channels per trip system but addresses the minimum total number of channels available.

Therefore, the proposed GGNS Action requirement does not refer to the number of channels available in a trip system. The changes proposed to Action 50 are consistent with the configurations assumed in the analysis presented in References 2 and 5.

The staff has reviewed the proposed changes and finds them to be acceptable.

The licensee has proposed that the time limits for Action Statements 51, 52, and 53 in Table 3.3.5-1 be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

In Table 4.3.5.1-1, the Channel functional Test frequency is extended from monthly to quarterly.

In addition, the calibration and testing frequency in footnotes (a) and (b) are changed from 31 to 92 days.

These changes are consistent with Reference 2 and are therefore acceptable.

2.3 Control Rod. flock Instrumentation The licensee has proposed modifications to the Control Rod Block Instrumentation 15.

The operability condition of Surveillance Requirement 4.3.6.1 will refer to a new footnote stating:

A channel may be placed in an operable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

A new Action Statement 64 is added to lable 3.3.6-1 for the Scram Discharge Volume and Reactor Coolant System Recirculation Flow Trip functions:

Action 64 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The proposed changes to TS Section 3/4.3.6, Control Rod Block Instrumentation, are consistent with the changes justified in Section 3.10 of Reference 1 and mark-ups on Attachment pages A-40 and A-42 of Reference 1.

The proposed TS changes create a new Action 64 instead of modifying the existing Action 62 as marked up in Reference 1.

As a result, a new Action requirement was needed to comply with the evaluation presented in Section 3.10 of Reference 1.

The staff has reviewed the proposed changes and finds them to be acceptable.

5-2.4 Radiation Monitorina Instrumentation The licensee has proposed modifications to the Radiation Monitoring Instrumentation TS.

In Table 3.3.7.1-1, footnote (h) has the following statement appended to it:

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

Part a. of Action 73 is revised to state:

With one of the required monitors in a trip system inoperable, place the inoperable channel in the downscale tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />;...

The licensee had requested a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A0T for Action 73 which applies to the Control Room Ventilation Radiation monitor. The request was based on the staff's approval of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A0T for this issue as part of the generic review of BWR6 improved standard technical specifications.

The staff, however, is not accepting the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A0T for this item separately from the improved standard technical specifications, and has changed the A0T to the currently approved 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> A0T.

This change was discussed with the licensee and is acceptable.

Part a. of Actions 74 and 75 is revised-to state:

With one of the required monitors in a trip system inoperable, place the inoperable channel in the downscale tripped condition 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />...

The Channel Functional Test frequency for the Control Room Ventilation Radiation Monitor, Containment and Drywell Ventilation Exhaust Radiation Monitor, Fuel Handling Area Ventilation Radiation Monitor, and Fuel Handling

. Area Pool Sweep Exhaust Radiation Monitor is changed from monthly to quarterly.

The proposed changes to TS Section 3/4.3.7.1 on pages 3/4 3-60 through 3 involve changes to the ST!s and A0Ts for the fuel Handling Area Ventilation Radiation Monitor, the Fuel Handling Area Pool Sweep Exhaust Radiation-Monitor, the Containment and Drywell Ventilation Exhaust Radiation Monitor,-

and the Control Room Ventilation Radiation Monitor.

The fuel Handling Area Ventilation Radiation Monitor, the Fuel Handling Area Pool Sweep Exhaust Radiation Monitor, and the Containment and Drywell Ventilation Exhaust Radiation Monitor instrumentation function both as l

Isolation Actuation instrumentation, as addressed in TS 3/4.3.2, and as radiation monitoring / alarm instrumentation, as addressed in TS 3/4.3.7.1, l

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These monitors use the same radiation detectors and analog conditioning circuitry to perform both of these functions.

Extensions to A0Ts and STls l

required by TS Section 3/4.3.2 were evaluated and requested in References 19 and 25 and approved by the NRC in Reference 24 for the Isolation Actuation function of the instrumentation.

The changes proposed in this amendment i

request to the TS 3/4.3.7.1 affect the radiation monitoring / alarm function of the instruments and are needed to ensure consistency between different specifications for the same equipment.

Discussion of the applicability of the analysis to these proposed changes was transmitted to the NRC in the Response to Question 9 of Reference 23.

The staff has reviewed these changes and finds them acceptable.

2.5 Plant Systems Actuation Instrumentation The licensee has proposed several modifications to the Plant Systems Actuation Instrumentation.

Footnote (a) in Table 3.3.8-1 is revised to state:

(a) A channel may be placed in an operable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the Reactor Vessel Water Level - High, level 8 instrumentation) during periods of required surveillance provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

The time limit in part a. of Action 130 in Table 3.3.8-1 is increased from I hour to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The time limit in Action 134 in Table 3.3.8-1 is increased from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The time limit in part a. of Action 135 is increased from I hour to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

in Table 4.3.8.1-1, the frequency of the Channel functional Tests for the Containment Spray System is decreased from monthly to quarterly.

Also, the frequency of the Channel Functional Tests for the Suppression Pool Make Up System is decreased from monthly to quarterly.

Footnote (a) is changed to read:

(a) Calibrate trip unit at least once per 92 days.

These modifications are consistent with Reference 1 and are therefore acceptable.

2.6 Reaclor Coolant System The licensee _ has proposed modifications to the Reactor Coolant System TS. A footnote is added to the operability conditions of Surveillance Require-ment 4.4.2.1.1, as follows:

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required. surveillance without placing the trip system in the tripped condition.

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The Channel functional Test frequency under Surveillance Requirement 4.4.2.1.1.a is decreased from 31 to 92 days. A footnote is added to the operability conditions of Surveillance Requirement 4.4.2.1.2, as follows:

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition.

The Channel functional Test frequency under Surveillance Requirement 4.4.2.1.2.a is decreased from 31 to 92 days. A footnote is added to the operability requirements of Surveillance Requirement 4.4.2.2.1, as follows:

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition.

The Channel functional Test frequency under Surveillance Requirement 4.4.2.2.1.a is decreased from 31 to 92 days. The proposed changes to the Reactor Coolant System TS are consistent with Reference 1 and are therefore acceptable.

2.7 Emeraency Core Coolina Systems The licensee has proposed several modifications to the Emergency Core Cooling Systems. Under Surveillance Requirement 4.5.3.1, a new operability condition is added which states:

c.

Two suppression pool water level instrumentation divisions, with I channel per division, OPERABLE # with the low water level alarm setpoint 212'8" per performance of a:

1.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.

CHANNEL FUNCTIONAL TEST at least once per 92 days, and 3.

CHANNEL CALIBRATION at least once per 18 months The corresponding footnote for this new section states:

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> during periods of required surveillance provided at least one other OPERABLE channel in the same system is monitoring that parameter.

The proposed changes to TS Section 4.5.3.1 on page 3/4 5-9 involve changes to l

STI and surveillance A0T for the wide-range suppression pool water level instrumentation. TS Section 4.5.3.1 addresses the surveillance requirements r

l for the monitoring and alarm functions of the wide-range suppression pool l

wcter level instrumentation, while TS Section 3/4.3.8.1 addresses the SPMS J

8 actuation function of this instrumentation.

The changes requested to TS Section 4.5.3.1 are consistent with the changes requested for TS Section 3/4.3.8.1 (SPHS system, suppression pool water level instrumentation).

The changes to TS Section 3/4.3.8.1 were evaluated and discussed in Section 3.7 of Reference 1.

The SPHS instrumentation controlled by 3/4.3 8.1 uses the same wide-range suppression pool water level trip units as are j

controlled by TS 4.5.3.1.

The proposed changes to TS Section 4.5.3.1 are, therefore, bounded by the analysis provided in Section 3.7 of Reference 1 and are needed for consistency. The requirements for narrow-range suppression pool water level instrumentation are not changed.

The staff has reviewed these modifications and finds them acceptable.

2.8 Modifications to Related Bases The licensee has proposed that the following statements be added to the Bases for the corresponding sections:

(1)

Recirculation Pump Trip Actuation Instrumentation Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with General Electric Report GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," February 1991.

(2)

Reactor Core Isolation Cooling System Actuation Instrumentation Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with General Electric Report GENE-770-06-2, " Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," February 1991.

(3)

Control Rod Block Instrumentation Specified surveillance and maintenance outage times have been determined in accordance with General Electric Report GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," February 1991.

(4) Radiation Monitoring Instrumentation Specified surveillance intervals and surveillance and maintenance outage times have been determined-in accordance with General Electric Report GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of Service Times for Selected Instrumentation Technical Specifications," February 1991.

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(5)

Plant Systems Actuation Instrumentation J

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with General Electric Report j

GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," February 1991.

(6) Safety / Relief Valves Specified surveillance intervals and surveillance outage times have been determined in accordance with General Electric Report GENE-770-06-1,

" Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

(7) Suppression Pool Specified surveillance intervals and surveillance outage times for the wide-range suppression pool water level instrumentation have been determined in accordance with General Electric Report GENE-770-06-1,

" Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specification,"

February 1991.

The staff has reviewed the proposed modifications and finds them to be acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Mississippi State official was notified of the proposed issuance of the amendment.

The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a l

facility component located within the restricted area as defined in 10 CFR i

Part 20 and changes surveillance requirements. The NRC staff has determined-that the amendment involves no significant increase in the amounts, and no L

significant change in the types, of any-effluents that may be released l

offsite, and that there is no significant increase in individual.or cumulative occupational radiation exposure. The Commission has previously issued a l

proposed finding that the amendment involves no significant hazards l

consideration, and there has been no public comment on such finding (57 FR 40212). -Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR t'

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51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 [pNCLUSION The Commission has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 SELECTED REFERENCES 1)

GE Report GENE-770-06-1, " Bases for Changes to Surveillance Test intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," February 1991.

2)

GE Report GENE-770-06-2, " Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-0f-Service Times for Selected Instrumentation Technical Specifications," February 1991.

4)

GE Topical Report NEDC-30851P-A, "BWR Owners Group Technical Specification Improvement Analyses for BWR Reactor Protection System,"

Harch 1988.

5)

GE Topical Report NEDC-30936P-A, "BWR Owners Group Technical Specification Improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation) Part 1," December 1988.

6)

GE Topical Report NEDC-30936P-A, " Technical Specification improvement Methodology (With Demonstration for BWR ECCS Actuation Instrumentation)

Part 2," December 1988.

7)

GE Topical Report NEDC-30851P-A, Supplement 1, " Technical Specification Improvement Analysis for BWR Control Red Block Instrumentation,"

October 1988, i

i 8)

GE Topical Report NEDC-30851P-A, Supplement 2, " Technical Specification l

Improvement Analysis for BWR lsolation-Instrumentation Common to RPS and l

ECCS Instrumentation," March 1989.

9)

GE Topical Report NEDC-31677P-A, " Technical Specification Improvement Analysis for BWR isolation Actuation Instrumentation," July 1990.

16)

Letter, 0.D. Kingsley, Jr. (GGNS) to USNRC, " Extension of RPS Instrumentation Surveillance Intervals and Allowed Outage Times (PCOL-88/09)," dated. June 30, 1988,

11 -

19)

Letter, W.T. Cottle (GGNS) to USNRC, " Extension of Instrumentation Surveillance Intervals and Allowed Outage Times (PCOL 91/12)," dated June 26, 1991.

22)

Letter, C.E. Rossi (NRR) to G.J. Beck (BWROG), " General Electric Company (GE) Topical Report GENE-770-06-2, ' Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications' (BWR RCIC Instrumentation),"

dated September 13, 1991.

23) letter, R.D. Binz IV (BWROG) to T.E. Hurley (NRR), "BWR Owners' Group Response to Questions on Topical Report GENE-770-06-1," dated December 20, 1991.

24)

Letter, P.W. O'Connor (NRR) to W.T. Cottle (Entergy), " Issuance of Amendment No. 97 to f acility Operating License No. NPF Grand Gulf Nuclear Station, Unit 1 (TAC No. H80700)," dated May 20, 1992.

25)

Letter, W.T. Cottle (GGNS) to USNRC, " Extension of Instrumentation Surveillance Intervals and Allowed Outage Times," dated April 22, 1992.

Principal Contributors:

H. Rathbun C. Doutt Date:

January 6, 1993 l

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