Text

R. E. Ginna - License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)
	ML092090538
Person / Time
Site:	Ginna
Issue date:	07/23/2009
From:	Emily Larson; Constellation Energy Group, Nuclear Generation Group, Ginna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	TSTF-286
	Download: ML092090538 (53)
	v • d • e

Eric Larson RE. Ginna Nuclear Power Plant, LLC Plant General Manager 1503 Lake Road Ontario, New York 14519-9364 585.771.5205 585.771.3900 Fax Eric.Larson @constellation.com CVonstell51ation Energyv-Nuclear Generation Group July 23, 2009 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)

In accordance with the provisions of 10 CFR 50.90, R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) is submitting a request for an amendment to revise the Technical Specification actions requiring suspension of operations involving positive reactivity addition and revise various notes precluding reduction in boron concentration.

The proposed changes would allow the introduction of positive reactivity to the core but would limit the addition such that the required margin to the Shutdown Margin (SDM) and refueling boron concentration limits will be maintained. The description and evaluation of the proposed changes are provided in the attached enclosure. In addition, marked up copies of the current Technical Specification pages are attached to the enclosure.

The changes proposed in this letter are similar to those documented in Industry Technical Specification Task Force (TSTF)-286, Revision 2, Define "Operations Involving Positive Reactivity Additions," which was approved by the NRC. Ginna has reviewed TSTF-286, Revision 2 and concluded that it is applicable to the R.E. Ginna Nuclear Power Plant (Ginna).

Differences between TSTF-286, Revision 2 and the proposed Technical Specification changes are noted and discussed in the attached enclosure.

This proposed change to the Technical Specifications and our determination of significant hazards have been reviewed by our Plant Operation Review Committee (PORC), and it has concluded that implementation of these changes will not result in an undue risk to the health and A.r(

Document Control'Desk July 23, 2009 Page 2 safety of the public. A copy of this letter with attachments has been provided to the appropriate state representative per 10CFR50.91 (b)(1).

We request that this change be approved by July 23, 2010. Once approved, the amendment shall be implemented within 60 days.

Should you have questions regarding this matter, please contact Thomas Harding at 585.771.5219, or Thomas.HardingJr@ Constellation.com.

Very truly yours, Eric A. Larson R.E. Ginna Nuclear Power Plant, LLC

Document Control Desk July 23, 2009 Page 3 STATE OF NEW YORK TO WIT:

COUNTY OF WAYNE I, Eric A. Larson, being duly sworn, state that I am Plant General Manager, R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), and that I am duly authorized to execute and file this request on behalf of Ginna LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Ginna LLC employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

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Subscribed and sworn before me, a Notary Public in and for the State York and County of Viathis ,oW,4day of.*/,

WITNESS my Hand and Notarial Seal:

My Commission Expires: RICHARD AA JOHNSON NOTARY PUBLIC, STATE OF NEWYORK O IN,W06082A344Y QUIALIFIED INWAYNE COUNTY Date MY COMMISSION EXPiRES 0c.4 . .. /

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Enclosure:

Evaluation of the Proposed Change cc: S. J. Collins, NRC D.V. Pickett, NRC Resident Inspector, NRC (Ginna)

P.D. Eddy, NYSDPS A. Peterson, NYSERDA R.E. Ginna Nuclear Power Plant, LLC

ENCLOSURE Evaluation of the Proposed Change TABLE OF CONTENTS 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedent 4.3 Significant Hazards Consideration 4.4 Conclusions

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

ATTACHMENTS

1. Technical Specification Page Markups R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 1 of 10

ENCLOSURE Evaluation of the Proposed Change 1.0

SUMMARY

DESCRIPTION This evaluation supports a request to amend Operating License No. DPR-18, for the R.E. Ginna Nuclear Power Plant (Ginna).

This proposed amendment revises several of the Required Actions in the Ginna Technical Specifications (TS) that require the suspension of operations involving positive reactivity additions or suspension of operations that would cause the reduction of the Reactor Coolant System (RCS) boron concentration. In addition, the proposed amendment adds or revises several notes that address reductions in RCS boron concentration. This proposed amendment revises these Required Actions and Limiting Condition for Operation (LCO) notes to allow small, controlled, safe insertions of positive reactivity, but limits the introduction of positive reactivity such that compliance with the required Shutdown Margin (SDM) or refueling boron concentration limits will still be satisfied.

This proposed change to the Ginna TS incorporates TSTF-286, Revision 2 (Reference 1). The TSTF is applicable to Ginna. During conditions in which the actions affected by the proposed changes may be required, various unit operations must be maintained and RCS temperature must be controlled. These activities may make it necessary to. add cooler water to the RCS (a positive reactivity change in most cases) or may involve inventory makeup from sources that are at a boron concentration less than that in the RCS. The proposed change provides the flexibility necessary for continued safe reactor operations, while limiting any potential for excess positive reactivity addition.

For example, operational considerations may make it necessary or prudent to use a different shutdown cooling loop from the one in operation. With the proposed changes, if the newly selected shutdown cooling loop is sampled and the boron concentration is slightly lower than that of the RCS, but sufficiently higher than the SDM and refueling boron concentration limits continue to be met, the switch to a different loop would be acceptable. Alternatively, if the shutdown cooling loop is at a lower or higher temperature than the RCS average temperature, but the reactivity effects are small enough to assure that the SDM and refueling boron concentration limits will continue to be met, the change to an alternate loop may be performed.

Another example of the type of activity that will be acceptable when the proposed changes are in effect is the addition of inventory to the RCS from the Refueling Water Storage Tank (RWST) during a refueling outage. Boron concentration in the RWST is controlled by TS between 2750 ppm and 3050 ppm. The RWST boron concentrations are cycle-specific and subject to change based on core design. Provided that the RWST boron concentration is sufficiently high to assure SDM and refueling boron concentration limits will continue to be met, an alternate supply of makeup to the RCS will be available from the RWST. These activities should not be precluded as long as the required SDM or refueling boron concentration is maintained.

R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 2 of 10

ENCLOSURE Evaluation of the Proposed Change 2.0 DETAILED DESCRIPTION The following are the proposed changes to Ginna's Limiting Condition of Operations (LCOs) based upon TSTF-286, Revision 2. The proposed changes to the Ginna TS are consistent with the changes proposed by TSTF-286, Revision 2 (Reference 1), unless otherwise stated. Where differences exist, an explanation is provided. Reference 2 provides clarification of the wording in Reference 1 in some cases. Ginna has utilized the wording in Reference 2 and has indicated this deviation from Reference 1 where applicable in the below discussion.

Adds a note to Required Action LCO 3.3.1.F.2 and LCO 3.3.1.H.2 tostate, "Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SDM."

Adds a note to Required Action LCO 3.3.1.J. 1 to state, "Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SDM."

Revises LCO Note 3.4.5, Note (a) to state, "No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1, and". The applicability of TSTF-286 LCO 3.4.5 is Mode 3 while the applicability of the Ginna LCO 3.4.5 is Modes 1, 2, and 3. However, Ginfia's LCO 3.4.5 Note (the location of the proposed change) is only applicable during the conditions when "Both reactor coolant pumps may be de-energized in Mode 3 for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period." Therefore, with regard to the Mode of applicability, the proposed revision is consistent with the TSTF-286. Additionally, the proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Action LCO 3.4.5.C.2 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1." The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises LCO note 3.4.6, Note (1.a) to state, "No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1; and". The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Action LCO 3.4.6.C. 1 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 3 of 10

ENCLOSURE Evaluation of the Proposed Change the SDM of LCO 3.1.1." The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises LCO note 3.4.7, Note (1.a) to state, "No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1; and". The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Action LCO 3.4.7.B. 1 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1." The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises LCO note 3.4.8, Note (1.a) to state, "No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1; and". The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Action LCO 3.4.8.B. 1 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1." The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Actions LCO 3.8.2.A.2.3 and LCO 3.8.2.B.3 to state, "Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration." TSTF-286, LCO 3.8.2 is for AC Sources - Shutdown.

The Ginna LCO 3.8.2 is for AC Sources - Modes 5 and 6. 'Since the TSTF-286 required action is applicable to Modes 5 and 6, the proposed revision to Ginna LCO 3.8.2 is' consistent with TSTF-286.

Revises Required Action LCO 3.8.5.A.2.3 to state, "Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration."

Revises Required Action LCO 3.8.8.A.2.3 to state, "Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration."

R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 4 of 10

ENCLOSURE Evaluation of the Proposed Change Revises Required Action LCO 3.8.10.A.2.3 to state, "Suspend operations involving Positive reactivity additions that could result in loss of required SDM or boron concentration."

Revises Required Action LCO 3.9.2.A.2 and LCO 3.9.2.C.2 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1." The change to LCO 3.9.2.C.2 is not addressed in TSTF-286 because Ginna's TS differs slightly from Standard TS, but is consistent with the philosophy and methodology of the TSTF changes. The proposed wording of the revisions varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises LCO 3.9.4 Note to state, "The required RHR loop may be removed from operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would cause introduction of coolant into the Reactor Coolant System (RCS) with boron concentration less than that required to meet the minimum required boron concentration of LCO 3.9.1." This note is applicable during Mode 6 with the water level > 23ft above the top of the reactor vessel flange, which is equivalent to the proposed TSTF-286 LCO 3.9.5 revision. The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Action LCO 3.9.4.A.1 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentrations less than required to meet the concentration of LCO 3.9.1." This is applicable during Mode 6 with the water level >

23ft above the top of the reactor vessel flange and the RHR loop requirements are not met, which is equivalent to the proposed TSTF-286 LCO 3.9.5.A. 1 Required Action.

The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

Revises Required Action LCO 3.9.5.B. 1 to state, "Suspend operations that would cause introduction of coolant into the RCS with boron concentrations less than required to meet the boron concentration of LCO 3.9.1." This is applicable during Mode 6 with the water level < 23 feet above the top of the reactor vessel flange and no RHR loop is in operation, which is equivalent to the proposed TSTF-286 LCO 3.9.6.B. 1 Required Action. The proposed wording of the revision varies from TSTF-286 as determined to be acceptable by Reference 2.

R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 5 of 10

ENCLOSURE Evaluation of the Proposed Change

3.0 TECHNICAL EVALUATION

Shutdown margin is a core design condition that can be ensured during operation through Control Rod (CR) positioning (control and shutdown groups) and through adjustment of the soluble boron concentration. In Modes 1 through 4, the minimum required SDM is assumed as an initial condition in safety analyses. This assumption ensures that specified acceptable fuel design limits are not exceeded for normal operation and anticipated operational occurrences, assuming that the highest worth CR remains fully withdrawn (and thus unavailable) following a reactor scram. In Modes 5 and 6, the reactivity condition of the core is consistent with the initial conditions assumed for the boron dilution accident analysis. The required boron concentration, in Mode 6, ensures that the keff of the core will remain within the required range of values during refueling operations.

Shutdown margin requirements provide sufficient reactivity margin to ensure that acceptable fuel design limits will not be exceeded for normal shutdown conditions or anticipated operational occurrences. As such, the SDM defines how much negative reactivity results from insertion all CRs, assuming the CR of highest reactivity worth remains fully withdrawn. In Modes 1 and 2 when critical, SDM is ensured by complying with TS 3.1.4, "Rod Group Alignment Limits," TS 3.1.5, "Shutdown Bank Insertion Limit," and TS 3.1.6, "Control Bank Insertion Limits."

In Mode 2 when subcritical and in Modes 3, 4, and 5, the SDM requirements provide enough negative reactivity to meet the assumptions of the safety analyses in the Updated Final Safety Analysis Report (UFSAR). In Modes 3 and 4, some rods may be withdrawn, which provides tripable rod worth in addition to preparing for reactor startup, but acceptable shutdown margin is maintained. Small changes in reactivity occur as a result of temperature changes associated with RCS inventory management or RCS temperature control. At the beginning of core life a positive moderator temperature coefficient is allowed by TS 3.1.3, "Moderator Temperature Coefficient (MTC)."

In Mode 6, the shutdown reactivity requirements are ensured by satisfying TS 3.9.1, Boron Concentration. During Mode 6, the limit on the boron concentrations of the RCS, the refueling canal, and the refueling cavity ensures that the reactor remains subcritical. Refueling boron concentration is the soluble boron concentration in the coolant having direct access to the reactor core during refueling. The soluble boron concentration, which offsets core reactivity, is measured by chemical analysis of a representative sample of the coolant. The refueling boron concentration limit is specified in the Core Operating Limits Report.

Two independent reactivity control systems are provided at Ginna. One of these systems maintains the core subcritical by the use of movable control and shutdown CRs. The other system uses the Chemical and Volume Control System (CVCS) that adjusts the soluble boric acid in the RCS. In Modes 1 and 2, the two independent reactivity control systems are used to compensate for the reactivity effects of the fuel and water temperature changes that accompany power level changes over the range from full load to no load. In addition, the CR together with R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 6 of 10

ENCLOSURE Evaluation of the Proposed Change the CVCS provide SDM during power operation and are capable of making the core subcritical rapidly enough to prevent exceeding acceptable fuel design limits, assuming that the CR of highest reactivity worth remains fully withdrawn. In Modes 3, 4, and 5, soluble boron is used to compensate for reactivity changes caused by temperature and reactor poisons, such as xenon, to maintain the reactor subcritical under shutdown conditions. Some rods are withdrawn in Mode 3 to prepare for reactor startup. In Mode 6, the CVCS is used to control boron concentration to meet required limits.

The main steam line break and boron dilution accidents are the most limiting analyses that establish the SDM value for LCO 3.1.1 and the minimum boron concentration requirement of LCO 3.9.1. For main steam line break accidents, if LCO 3.1.1 is not met, there is a potential to exceed the departure from nucleate boiling ratio limit and the required actions of LCO 3.1.1 are necessary to restore compliance with the LCO. For the boron dilution accident, if LCO 3.1.1 or 3.9.1 are not met, the minimum required time assumed for operator action to terminate dilution may no longer be sufficient, and the required actions of LCO 3.1.1 or LCO 3.9.1 are necessary to restore compliance with the LCO.

The actions and notes that precluded positive reactivity additions and reduction in boron concentration were intended to ensure that under the specified plant conditions, further power increases or reductions in the margin to core criticality were precluded. The proposed change allows the small reactivity effects that result from temperature or boron concentration fluctuations associated with RCS inventory management or temperature control to be performed, provided the minimum SDM of LCO 3.1.1 or the minimum boron concentration of LCO 3.9.1 is maintained. The changes to notes and actions continue to provide assurance that the assumptions of the most limiting accident analyses are maintained. Therefore, necessary activities that involve additions to the RCS of cooler water (a positive reactivity effect in most cases) or that may involve makeup from borated sources of water that are at boron concentrations less than the RCS boron concentration, should not be precluded as long as the required margin to criticality, the required SDM, or refueling boron concentration limits are not adversely affected.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria NRC approved Generic Changes to the Standard TS, TSTF-286, Revision 2, Define "Operations Involving Positive Reactivity Changes" 4.2 Precedent The following plants have received approval for adopting TSTF-286:

H. B. Robinson Unit 2 (ADAMS Accession Number ML010810282)

R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 7 of 10

ENCLOSURE Evaluation of the Proposed Change Callaway Unit 1 (ADAMS Accession Number ML020220051)

Wolf Creek Generating Station (ADAMS Accession Number ML021290254)

Catawba Nuclear Station, Units 1 & 2 (ADAMS Accession Number ML032110122)

McGuire Nuclear Station Units 1 & 2 (ADAMS Accession Number ML032110073)

Calvert Cliffs Nuclear Power Plant, Units 1 & 2 (ADAMS Accession Number ML040760287) 4.3 Significant Hazards Consideration R.E. Ginna Nuclear Power Plant, LLC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The Technical Specifications (TS) addressed in this proposed change prevent inadvertent addition of positive reactivity which could challenge the shutdown margin of the reactor core.

The current TS contain rigid requirements that sometimes pose operational difficulties without significantly increasing safety. The intent of the change is to allow small, controlled, and safe insertions of positive reactivity that are now categorically prohibited to allow operational flexibility. These new activities could result in a slight change in the probability of an event occurring because Reactor Coolant System (RCS) manipulations that are currently prohibited would now be allowed. However, to preclude an increase in the probability of a reactivity addition accident, RCS manipulations are rigidly controlled to ensure that the reactivity remains within the required shutdown margin.

The proposed change does not permit the shutdown margin to be reduced below that required by the TS. While the proposed change will permit changes in the discretionary boron concentration above the TS requirements, this excess concentration is not credited in the Updated Final Safety Analysis Report accident analysis. Because the initial conditions assumed in the safety analysis are preserved, no increase in the consequences of an accident previously evaluated would occur.

In addition, small temperature changes in the RCS impose reactivity changes by means of the moderator temperature coefficient of reactivity. These small changes are within the required shutdown margin which also bounds the reactivity addition accident analysis ensuring there is no increase in the consequence of an accident previously evaluated.

R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 8 of 10

ENCLOSURE Evaluation of the Proposed Change Therefore the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

This proposed amendment allows for minor plant operational adjustments without adversely impacting the safety analysis required shut down margin. It does not involve any change to plant equipment or the shutdown margin requirements in the TS, and no new accident precursors are created.

Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The margin of safety in Modes 3, 4, 5, and 6 is preserved by the TS required shutdown margin which prevents a return to criticality. The proposed change will permit reductions in the discretionary shutdown margin only within the limits of the TS, thereby maintaining the margin of safety within the accident analysis.

Therefore, the proposed change will not involve a significant reduction in the margin of safety.

4.4 Conclusions As discussed above, the proposed changes are based on TSTF-286, Revision 2. These changes revise actions that either require suspension of operations involving positive reactivity additions, or preclude reduction in boron to a concentration less than that of the RCS. The proposed changes limit the introduction into the RCS of reactivity more positive than that required to meet the required SDM or refueling boron concentrations, as applicable. The operational flexibility allowed in the proposed license amendment will be performed under administrative controls in order to limit the potential for excess positive reactivity additions. Therefore, the proposed changes are deemed safe and acceptable.

5.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 9 of 10

ENCLOSURE Evaluation of the Proposed Change amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c) (9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

6.0 REFERENCES

1. TSTF-286, Technical Specification Task Force Improved Standard Technical Specification Change Traveler, Revision 2.

2. Memorandum from J. N. Donohew (NRC) to R. A. Gramm (NRC), dated May 16, 2003, Comanche Peak Steam Electric Station, Units 1 and 2 - Licensee's Agreement to Revised Wording in Proposed License Amendment Involving Positive Reactivity Additions (TAC Nos. MB6890 and MB6891).

R.E. Ginna Nuclear Power Plant, LLC July 23, 2009 Page 10 of 10

Attachment 1 Technical Specification Page Markups

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

-NOTE-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one channel referenced in Table 3.3.1-1 inoperable, for the channel(s).

OR Two source range channels inoperable.

B. As required by Required B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Action A.1 and referenced OPERABLE status.

by Table 3.3.1-1.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition B not AND met.

C.2 Initiate action to fully insert 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months all rods.

AND C.3 Place Control Rod Drive 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months System in a condition incapable of rod withdrawal.

R.E. Ginna Nuclear Power Plant 3.3.1-1 Amendmentx,

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Action X.1 and referenced ------- -----

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months E. As requirld by Required E. 1 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Action k.1", and referenced to < 5E-11 amps.

by Table 3.3.1-1.

- NOTE -

Required Action E.2 is not applicable when:

/ a. Two channels are inoperable, or

b. THERMAL POWER is

< 5E-11 amps.

Increase THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to Ž 8% RTP.

+

F. As required by Required SiOpen RTBs and RTBBs Immediately upon Action A. 1 and referenced upon discovery of two discovery of two by Table 3.3.1-1. inoperable channels. inoperable channels AND F.2 Suspend operations Immediately involving positive reactivity additions.

AND F.3 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

R.E. Ginna Nuclear Power Plant 3.3.1-2 Amendmentýý

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition D, E, or F is not met.

H. As required by Required H.1 Restore at least one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced channel to OPERABLE discovery of two by Table 3.3.1-1. status upon discovery of two inoperable channels inoperable channels.

/IN S e(L"T"l AND

".

upn H.2 Suspend operations Immediately involving positive reactivity additions.

AND H.3 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

Required Action and 1.1 Initiate action to fully insert Immediately associated Completion all rods.

Time of Condition H not met. AND 1.2 Place the Control Rod Drive 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months System in a condition incapable of rod withdrawal.

J. As required by Required J.1 Suspend operations Immediately Action A. 1 and referenced J! involving poiiereactivity

~AND J.2 Perform SR 3.1.1.1. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter R.E. Ginna Nuclear Power Plant 3.3.1-3 Amendmenllaý

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required K.1 Action A.1 and referenced ---- -------

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months L. Required Action and L.1 Reduce THERMAL POWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion to < 8.5% RTP.

Time of Condition K not met.

M. As required by Required M.1 Action A.1 and referenced --------------

by Table 3.3.1-1. - NOTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in tfip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months N. As required by Required N.1 Restore channel to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action A.1 and referenced OPERABLE status.

by Table 3.3.1-1.

0. Required Action and 0.1 Reduce THERMAL POWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I associated Completion to < 30% RTP.

Time of Condition M or N not met.

P. As required by Required P.I Action A.1 and referenced -----------

by Table 3.3.1-1. N-OTE -

The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels.

Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months R.E. Ginna Nuclear Power Plant 3.3.1-4 Amendmentk7""

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME Q. Required Action and aQ.1 Reduce THERMAL POWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion to < 50% RTP.

lime of Condition P not met. AND Q.2.1 Verify Steam Dump System 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months is OPERABLE.

OR Q.2.2 Reduce THERMAL POWER 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months to < 8% RTP.

R. As required by Required R.1 Action A.1 and referenced ------- -----

by Table 3.3.1-1. - NOTE -

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to OPERABLE 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months status.

S. As required by Required S.1 Verify interlock is in required 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action A.1 and referenced state for existing plant by Table 3.3.1-1. conditions.

OR S.2 Declare associated RTS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Function channel(s) inoperable.

R.E. Ginna Nuclear Power Plant 3.3.1-5 AmendmentX.

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME T. As required by Required T.1 Action A.1 and referenced by Table 3.3.1-1. - NOTE -

1. One train may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing, provided the other train is OPERABLE.

2. One RTB may be bypassed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for maintenance on undervoltage or shunt trip mechanisms, provided the other train is OPERABLE.

Restore train to OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months status.

U. As required by, Required U.1 Restore at least one trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced mechanism to OPERABLE discovery of two by Table 3.3.1-1. status upon discovery of two inoperable trip RTBs with inoperable trip mechanisms mechanisms.

AND U.2 Restore trip mechanism to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

V. Required Action and V.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition R, S, T, or U not met.

W. As required by Required W.1 Restore at least one trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Action A.1 and referenced mechanism to OPERABLE discovery of two by Table 3.3.1-1. status upon discovery of two inoperable trip RTBs with inoperable trip mechanisms mechanisms.

AND R.E. Ginna Nuclear Power Plant 3.3.1-6 Amend me no-111"

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME W.2 Restore trip mechanism or 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months train to OPERABLE status.

X. Required Action and X.1 Initiate action to fully insert Immediately associated Completion all rods.

Time of Condition W not met. AND X.2 Place the Control Rod Drive 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months System in a Condition incapable of rod withdrawal.

SURVEILLANCE REQUIREMENTS

- NOTE -

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2 - NOTE -

Required to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is Ž 50% RTP.

Compare results of calorimetric heat balance 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculation to Nuclear Instrumentation System (NIS) channel output and adjust if calorimetric power is

> 2% higher than indicated NIS power.

SR 3.3.1.3 -NOTE-

1. Required to be performed within 7 days after THERMAL POWER is Ž_50% RTP but prior to exceeding 90% RTP following each refueling and if the Surveillance has not been performed within the last 31 EFPD.

2. Performance of SR 3.3.1.6 satisfies this SR.

Compare results of the incore detector measurements 31 effective full to NIS AFD and adjust if absolute difference is Ž_3%. power days (EFPD)

R.E. Ginna Nuclear Power Plant 3.3.1-7 Amendmente

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.4 Perform TADOT. 31 days on a STAGGEREDTEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.1.6 -NOTE-Not required to be performed until 7 days after THERMAL POWER is Ž_50% RTP, but prior to exceeding 90% RTP following each refueling.

Calibrate excore channels to agree with incore 92 EFPD detector measurements.

-- NOTE -

SR 3.3.1.7 Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entering MODE 3.

Perform COT. 92 days

- NOTE -

SR 3.3.1.8

1. Not required for power range and intermediate range instrumentation until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reducing power < 6% RTP.

2. Not required for source range instrumentation until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reducing power < 5E-11 amps.

Perform COT. 92 days SIR3.3.1.9 SR 3..1.9-

NOTE NOE---- - -- -- -- -------

Setpoint verification is not required.

Perform TADOT. 92 days R.E. Ginna Nuclear Power Plant 3.3.1-8 Amendmente

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY

-OTE- -

SR 3.3.1.10 - NOTE -

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.11 Perform TADOT. 24 months

- NOTE -

SR 3.3.1.12 Setpoint verification is not required.

Perform TADOT. Prior to reactor startup if not performed within previous 31 days SR 3.3.1.13 Perform COT. 24 months R.E. Ginna Nuclear Power Plant 3.3.1-9 Amendment9l",

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

1. Manual Reactor Trip 1,2, 2 B,C SR 3.3.1.11 NA 3(b), 4 (b), 5 (b)

2. Power Range Neutron Flux I a. High 1,2 4 D,G SR 3.3.1.1 109.27%

SR 3.3.1.2 RTP SR 3.3.1.7 SR 3.3.1.10

b. Low 1(c), 2 4 D,G SR 3.3.1.1 _ 29.28%

SR 3.3.1.8 RTP SR 3.3.1.10

3. Intermediate Range 1(c), 2 2 E,G SR 3.3.1.1 (d)

Neutron Flux SR 3.3.1.8 SR 3.3.1.10

4. Source Range 2 (e) 2 F,G SR 3.3.1.1 (d)

Neutron Flux SR 3.3.1.8 SR 3.3.1.10 3 (b), 4 (b), 5 (b) H,I SR 3.3.1.1 (d)

SR 3.3.1.7 SR 3.3.1.10 (0, (f), (f) J SR 3.3.1.1 NA 3 4 5 SR 3.3.1.10

5. Overtemperature AT 1,2 D,G SR 3.3.1.1 Refer to SR 3.3.1.3 Note 1 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10

6. Overpower AT 1,2 D,G SR 3.3.1.1 Refer to SR 3.3.1.7 Note 2 SR 3.3.1.10 R.E. Ginna Nuclear Power Plant 3.3.1-10 Amendmentg-ý

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

7. Pressurizer Pressure

a. Low 1 (g) 4 K,L SR 3.3.1.1 _1791.3 SR 3.3.1.7 psig SR 3.3.1.10

b. High 1,2 3 D,G SR 3.3.1.1 *52396.2 SR 3.3.1.7 psig SR 3.3.1.10

8. Pressurizer Water 1,2 3 D,G SR 3.3.1.1 _<96.47%

Level-High SR 3.3.1.7 SR 3.3.1.10

9. Reactor Coolant Flow-Low

a. Single Loop I(h) 3 per loop M,O SR 3.3.1,1 _>89.86%

SR 3.3.1.7 SR 3.3.1.10

b. Two Loops 10') 3 per loop K,L SR 3.3.1.1 >_89.86%

SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Pump (RCP)

Breaker Position

a. Single Loop j(h) 1 per RCP N,O SR 3.3.1.11 NA

b. Two Loops 1U) 1 per RCP K,L SR 3.3.1.11 NA 2 per bus K,L SR 3.3.1.9 (d)

11. Undervoltage- l(g)

Bus 11A and 11B SR 3.3.1.10

12. Underfrequency- l(g) 2 per bus K,L SR 3.3.1.9 - 57.5 HZ Bus 11A and 11B SR 3.3.1.10 R.E. Ginna Nuclear Power Plant 3.3.1-11 Amendmenpil",

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(a)

13. Steam Generator 1,2 3 per SG D,G, SR 3.3.1.1 Ž>13.88%

(SG) Water Level-

SR 3.3.1.7 Low Low SR 3.3.1.10

14. Turbine Trip

a. Low Autostop 1(k)(I) 3 PQ SR 3.3.1.10 (d)

Oil Pressure SR 3.3.'1.12

b. Turbine Stop 1(k)(I) 2 PQ SR 3.31..12 NA Valve Closure

15. Safety Injection (SI) 1, 2 2 R,V SR 3.3.1.11 NA Input from Engineered Safety Feature Actuation System (ESFAS)

R.E. Ginna Nuclear Power Plant 3.3.1-12 AmendmentX

RTS Instrumentation 3.3.1 Table 3.3.1-1 Reactor Trip System Instrumentation APPLICABLE MODES OR LIMITING OTHER SAFETY SPECIFIED REQUIRED SURVEILLANCE SYSTEM FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS SETTINGS(aI

16. Reactor Trip System Interlocks

a. Intermediate 2(e) 2 S,V SR 3.3.1.10 55E-11 Range SR 3.3.1.13 amp Neutron Flux, P-6

b. Low Power 1W) 4 (power range S,V SR 3.3.1.10 < 8.0% RTP Reactor Trips only) SR 3.3.1.13 Block, P-7 I c. Power Range 4 S,V SR 3.3.1.10 _ 29.0%

Neutron Flux, SR 3.3.1.13 RTP P-8 1(h)

d. Power Range 4 S,V SR 3.3.1.10 _ 50.0%

Neutron Flux, SR 3.3.1.13 RTP P-9 4 S,V SR 3.3.1.10 < 8.0% RTP 1 (k)

SR 3.3.1.13

e. Power Range 4 S,V SR 3.3.1.10 6.0% RTP 1 (c), 2 Neutron Flux, SR 3.3.1.13 P-10

17. Reactor Trip 1,2 2 trains T,V SR 3.3.1.4 NA Breakers(') 3 (b), 4 (b) 5 (b) 2 trains W,X SR 3.3.1.4 NA

18. Reactor Trip 1,2 1 each per RTB U,V SR 3.3.1.4 NA Breaker 3 (b), 4 (b), 5 (b) 1 each per RTB W,X SR 3.3.1.4 NA Undervoltage and Shunt Trip Mechanisms

19. Automatic Trip Logic 1,2 2 trains R,V SR 3.3.1.5 NA 3 (b), 4 (b), 5 (b) 2 trains W,X SR 3.3.1.5 NA R.E. Ginna Nuclear Power Plant 3.3.1-13 Amendmente

RTS Instrumentation 3.3.1 (a)

A channel is OPERABLE when both of the following conditions are met:

1. The absolute difference between the as-found Trip Setpoint (TSP) and the previous as-left TSP is within the COT Acceptance Criteria. The COT Acceptance Criteria is defined as:

jas-found TSP - previous as-left TSPI -<COT uncertainty The COT uncertainty shall not include the calibration tolerance.

2. The as-left TSP is within the established calibration tolerance band about the nominal TSP. The nominal TSP is the desired setting and shall not exceed the Limiting Safety System Setting (LSSS). The LSSS and the established calibration tolerance band are defined in accordance with the Ginna Instrument Setpoint Methodology. The channel is considered operable even if the as-left TSP is non-conservative with respect to the LSSS provided that the as-left TSP is within the established calibration tolerance band.

(b) With Control Rod Drive (CRD) System capable of rod withdrawal or all rods not fully inserted.

(c) THERMAL POWER < 6% RTP.

(d) UFSAR Table 7.2-3.

(e) Both Intermediate Range channels < 5E-11 amps.

(f) With CRD System incapable of withdrawal and all rods fully inserted. In this condition, the Source Range Neutron Flux function does not provide a reactor trip, only indication.

(g) THERMAL POWER >8.5% RTP.

(h) THERMAL POWER >30% RTP.

(I) THERMAL POWER Ž8.5% RTP and Reactor Coolant Flow-Low (Single Loop) trip Function blocked.

THERMAL POWER Ž 8.5% RTP and RCP Breaker Position (Single Loop) trip Function blocked.

(k) THERMAL POWER > 8% RTP, and either no circulating water pump breakers closed, or, condenser vacuum < 20".

(I) THERMAL POWER Ž 50% RTP, 1 of 2 circulating water pump breakers closed, and condenser vacuum > 20".

(mn) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

R.E. Ginna Nuclear Power Plant 3.3.1-14 AmendmentX"

RTS Instrumentation 3.3.1 Table 3.3.1-1 (Note 1)

Overtemperature AT

- NOTE -

The Overtemperature AT Function Limiting Safety System Setting is defined by:

Overtemperature AT < AT0 {K1 + K2 (P-P') - K3 (T-T') [(1+r 1s) / (1+T2s)] - f,(Al)}

Where:

AT is measured RCS AT, OF.

AT0 is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec"1 .

T is the measured RCS average temperature, OF.

T' is the nominal Tavg at RTP, OF.

P is the measured pressurizer pressure, psig.

P' is the nominal RCS operating pressure, psig.

K1 is the Overtemperature AT reactor trip setpoint, [*].

K2 is the Overtemperature AT reactor trip depressurization setpoint penalty coefficient, [*]/psi.

K3 is the Overtemperature AT reactor trip heatup setpoint penalty coefficient, [*]/OF.

Tr1 is the measured lead time constant, 1*1 seconds.

-T2 is the measured lag time constant, [* seconds.

f(AI) is a function of the indicated difference between the top and bottom detectors of the Power Range Neutron Flux channels where qt and qb are the percent power in the top and bottom halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

f1 (AI) = *] [*- (qt-b) when qt - qb!< [*]% RTP fl(AI) = 0% of RTP when [*] % RTP < qt - qb*]%RTP fl(AI) = [*] {(qt - qb)- [*] when qt - qb > [*1%RTP

These values denoted with [*] are specified in the COLR.

R.E4 Ginna Nuclear Power Plant 3.3.1-15 Amendment'01,

RTS Instrumentation 3.3.1 Table 3.3.1-1 (Note 2)

Overpower AT

.- NOTE -

The Overpower AT Function Limiting Safety System Setting is defined by:

Overpower AT < AT0 {K4 - K5 (T-T') - K6 [(T3sT),I ('3s+1)] - f2(AI)}

Where:

AT is measured RCS AT, OF.

ATo is the indicated AT at RTP, OF.

s is the Laplace transform operator, sec-1 .

T is the measured RCS average temperature, 'F.

T' is the nominal Tavg at RTP, IF.

K4 is the Overpower AT reactor trip setpoint, [*].

K5 is the Overpower AT reactor trip heatup setpoint penalty coefficient which is:

[*]/OF for T < T' and;

[*]/OF for T _>T'.

K6 is the Overpower AT reactor trip thermal time delay setpoint penalty which is:

[*]/OF for increasing T and;

[*]/OF for decreasing T.

'U3 is the measured impulse/lag time constant, [*] seconds, f2(AI) = [1

These values denoted with [*] are specified in the COLR.

R.E. Ginna Nuclear Power Plant 3.3.1-16 Amend menwrl",

RCS Loops - MODES I <_8.5% RTP, 2, and 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODES 1

8.5% RTP, 2, and 3 LCO 3.4.5 Two RCS loops shall be OPERABLE and one loop shall be in operation.

- NOTE -

Both reactor coolant pumps may be de-energized in MODE 3 for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

S . .a. operations ar eermitted that wo'lcause reduc of the RC_

-LN *,LT "boro concentration; qd ..

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

APPLICABILITY: MODES 1

8.5% RTP, MODES 2 and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I A. One RCS loop A.1 Verify SDM is within limits Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable, specified in the COLR.

AND A.2 Restore inoperable RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months loop to OPERABLE status.

B. Required Action and B.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

R.E. Ginna Nuclear Power Plant 3.4.5-1 .AmendmentSBý

RCS Loops - MODES 1 < 8.5% RTP, 2, and 3 3.4.5 CONDITION REQUIRED ACTION I COMPLETION TIME C. Both RCS loops C.1 De-energize all CRDMs. Immediately inoperable.

AND OR C.2 L Susp d al1Qper aon*," Immediately No RCS loop in operation. Involvin redationf R' bolcon tratt. IN 4 SQ T AND C.3 Initiate action to restore one Immediately RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify steam generator secondary side water levels 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are _>16% for two RCS loops.

SR 3.4.5.3 Verify correct breaker alignment and indicated power 7 days are available to the required RCP that is not in operation.

R.E. Ginna Nuclear Power Plant 3.4.5-2 AmendmenUW'

RCS Loops - MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops - MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.

- NOTE -

1. All reactor coolant pumps (RCPs) and RHR pumps may be de-energized for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. operations permittehat woulllýuse reducltn of the RC Qron conce neation;" an N N

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. No RCP shall be started with any RCS cold leg temperature less than or equal to the LTOP enable temperature specified in the PTLR unless:

a. The secondary side water temperature of each steam generator (SG) is _<50°F above each of the RCS cold leg temperatures; or

b. The pressurizer water volume is < 324 cubic feet (38% level).

APPLICABILITY: MODE 4.

ACTIONS CONDITION. REQUIRED ACTION COMPLETION TIME A. One RCS loop A.1 Initiate action to restore a Immediately inoperable, second loopto OPERABLE status.

AND Two RHR loops inoperable.

R.E. Ginna Nuclear Power Plant 3.4.6-1 Amendment.ge-

RCS Loops

- MODE 3.4.64 REQUIRED B. ACTION One RHR inoperable.loop

NOTE AND Required Action applicable if B-1 is not all RCS and Two RCS loops RHR loops are inoperable inoperable. and Condition C

is entered.

B.1 Be in MODE 5.

C. All RCS and RHR 124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months inoperable. loops OR No RCS or RHR operation. loop in initiate loop to action to re .store OPERABLE one status immediately and operation. I sURVEILLANCE REOU'REMENTS SURVEILLANCE SR 3.4.61 Verify one RHR or RCS loop is in operation.

SR 3,4.6.2 Verify SG secondary each required Side water ..Ievel is

> 16% for RCS loop..

SR 3,4.6.3 Verify correct I are available breaker alignment nd indicated power. *,v -I A, to the required I oaYS ,*

operation. Pumpa that is not in R.E. Ginna Nuclear Power Plant 3.4.6-2 Amendment-W

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a. One additional RHR loop shall be OPERABLE; or

b. The secondary side water level of at least one steam generator (SG) shall be > 16%.

- NOTE -

1. The RHR pump of the loop in operation may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

(Qperati1 NQa. a re per--fiýdthat wif&ause reduc of the oCS on con tration; a .

b. Core outlet temperature is maintained at least 10'F below saturation temperature.

2. One required RHR loop may be inoperable for < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

3. No reactor coolant pump shall be started with one or more RCS cold leg temperatures less than or equal to the LTOP enable temperature specified in the PTLR unless:

a. The secondary side water temperature of each SG is < 50°F above each of the RCS cold leg temperatures; or

b. The pressurizer water volume is < 324 cubic feet (38% level).

4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY: MODE 5 with RCS loops filled.

R.E. Ginna Nuclear Power Plant 3.4.7-1 AmendmentW-

RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop A.1 Initiate action to restore a Immediately inoperable, second RHR loop to OPERABLE status.

AND OR Both SGs secondary side water levels not within A.2 Initiate action to restore Immediately limits, required SG secondary side water levels to within limits.

B. Both RHR loops B.1 (Sus

{ v*olving all o cton ions

,S]

Immediately inoperable.

bo r'nconcentraT.

~LNSeA~F 3 AND No RHR loop in operation.

B.2 Initiate action to restore one Immediately RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is > 16% in the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months required SG.

SR 3.4.7.3 Verify correct breaker alignment and indicated power 7 days are available to the required RHR pump that is not in operation.

R.E. Ginna Nuclear Power Plant 3.4.7-2 AmendmentW

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

- NOTE -

1. All RHR pumps may be de-energized for < 15 minutes when switching from one loop to another provided:

a.*Loper--ati~rae permiIStat Wouldý! a reduc of) tho~ , S boron ntration;- , --. " ,,

,Z 4

b. Core outlet temperature is maintained at least 10°F below saturation temperature; and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One RHR loop may be inoperable for < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop A.1 Initiate action to restore Immediately inoperable. RHR loop to OPERABLE status.

B. Both RHR loops B.1 / Suspen 11oper Qns Immediately inoperable. (I>halving re tion inCS OR bord*_oncentr ' n L3 AND No RHR loop in operation.

R.E. Ginna Nuclear Power Plant 3.4.8-1 Amend ment,80-"'

RCS Loops - MODE 5, Loops Not Filled 3.4.8 CONDITION REQUIRED ACTION COMPLETION TIME B.2 Initiate action to restore one Immediately RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 Verify correct breaker alignment and indicated power 7 days are available to the RHR pump that is not in operation.

R.E. Ginna Nuclear Power Plant 3.4.8-2 Amendment1w

AC Sources - MODES 5 and 6 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - MODES 5 and 6 LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified independent offsite power circuit connected between the offsite transmission network and each of the onsite 480 V safeguard buses required by LCO 3.8.10, "Distribution Systems -

MODES 5 and 6"; and

b. One emergency diesel generator (DG) capable of supplying one train of the onsite 480 V safeguard bus(es) required by LCO 3.8.10.

APPLICABILITY: MODES 5 and 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Offsite power to 80-one or morerequred -- NOTE--

NOTE -

more required 480 V Enter applicable Conditions safeguards bus(es) and Required Actions of inoperable. LCO 3.8.10, with one required train de-energized as a result of Condition A.

A.1 Declare affected required Immediately feature(s) inoperable.

OR R.E. Ginna Nuclear Power Plant 3.8.2-1 AmendmentW

AC Sources - MODES 5 and 6 3.8.2 CONDITION REQUIRED ACTION COMPLETION TIME A.21 SupndCR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Initiate tion to "spend Immediately oration vovin lsitive reac ty ad di ns .

AND A.2.4 Initiate action to restore Immediately required offsite power circuit to OPERABLE status.

B. DG to the required 480 V B.1 Suspend CORE Immediately safeguards bus(es) ALTERATIONS.

inoperable.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies.

AND Nr S LzT B.3 Initia action suspe Immediately t'Ieratio involvi osit ,

re ivity a ons.

AND B.4 Initiate action to restore Immediately required DG to OPERABLE status.

R.E. Ginna Nuclear Power Plant 3.8.2-2 AmendmentW

AC Sources - MODES 5 and 6 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 For AC sources required to be OPERABLE, the In accordance with following SRs are applicable: applicable SRs SR 3.8.1.1 SR 3.8.1.4 SR 3.8.1.2 SR 3.8.1.5 R.E. Ginna Nuclear Power Plant 3.8.2-3 AmendmentW

DC Sources - MODES 5 and 6 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - MODES 5 and 6 LCO 3.8.55 DC electrical power sources shall be OPERABLE to support the DC electrical power distribution subsystem required by LCO 3.8.10, "Distribution Systems - MODES 5 and 6."

APPLICABILITY: MODES 5 and 6.

ACTIONS CONDITION I REQUIRED ACTION COMPLETION TIME A. One or more required DC A.1 Declare affected required Immediately electrical power source(s) feature(s) inoperable.

inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND GIZ~.,f.T8 Immediately A.2.4 Initiate action to restore Immediately required DC electrical power source(s) to OPERABLE status.

R.E. Ginna Nuclear Power Plant 3.8.5-1 AmendmentJW

DC Sources - MODES 5 and 6 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.8.5.1 For DC sources required to be OPERABLE, SR 7T FREQUENCY In accordance with 3.8.4.1 is applicable. applicable SR R.E. Ginna Nuclear Power Plant 3.8.5-2 AmendmentW'-

AC Instrument Bus Sources - MODES 5 and 6 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 AC Instrument Bus Sources - MODES 5 and 6 LCO 3.8.8 AC instrument bus power sources shall be OPERABLE to support the onsite Class 1E AC instrument bus electrical power distribution subsystem required by LCO 3.8.10, "Distribution Systems - MODES 5 and 6."

APPLICABILITY: MODES 5 and 6.

ACTIONS CONDITION I REQUIRED ACTION COMPLETION TIME A. One or more required AC A.1 Declare affected required Immediately instrument bus power feature(s) inoperable.

source(s) inoperable.

A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Inittite*,ctio to-9ýippe*"*ý

/ NS LrtT Immediately opb)e rat ion

.involvi n g Ptw*tive.

rea vity~addýit'orm% y AND A.2.4 Initiate action to restore Immediately required AC instrument bus power source(s) to OPERABLE status.

R.E. Ginna Nuclear Power Plant 3.8.8-1 AmendmentW

AC Instrument Bus Sources - MODES 5 and 6 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct static switch alignment to required AC 7 days instrument bus(es).

SR 3.8.8.2 Verify correct Class 1E CVT alignment to the required 7 days AC instrument bus.

R.E. Ginna Nuclear Power Plant 3.8.8-2 Amendment,86"

Distribution Systems - MODES 5 and 6 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - MODES 5 and 6 LCO 3.8.10 The necessary trains(s) of the following electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE:

a. AC power;

b. AC instrument bus power; and

c. DC power.

APPLICABILITY: MODES 5 and 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately electrical power supported required distribution train(s) feature(s) inoperable.

inoperable.

OR R.E. Ginna Nuclear Power Plant 3.8.10-1 Amendment,80ý'

Distribution Systems - MODES 5 and 6 3.8.10 CONDITION REQUIRED ACTION COMPLETION TIME A.2.1Susped COR A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND

i eNrLT-A.2.3 Initiate-9ion to end Immediately

prations l*ving vgp ye e..a ct!*a~pd d itid-°1&-

AND A.2.4 Initiate actions to restore Immediately required electrical power distribution train(s) to OPERABLE status.

AND A.2.5 Declare associated required Immediately residual heat removal loop(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to 7 days required electrical power distribution trains.

R.E. Ginna Nuclear Power Plant 3.8.10-2 Amendmenolor

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range neutron flux monitors shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION I REQUIRED ACTION I COMPLETION TIME A. One source range A.1 Suspend CORE Immediately neutron flux monitor ALTERATIONS.

inogperable.

AND (Trr%.r CT A

Suspend' react .. immediately B. Two source range B.1 Initiate action to restore one Immediately neutron flux monitors source range neutron flux inoperable. monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter C. No audible count rate. C.1 Suspend CORE Immediately ALTERATIONS.

u pstr *.2 Immediately AN.DD R.E. Ginna Nuclear Power Plant 3.9.2-1 Amendmente

Nuclear Instrumentation 3.9.2 CONDITION REQUIRED ACTION COMPLETION TIME C.3 Perform SR 3.9.1.1 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 -NOTE- -

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION. 24 months R.E. Ginna Nuclear Power Plant 3.9.2-2 AmendmenLe

RHR and Coolant Circulation - Water Level ; 23 Ft 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation - Water Level > 23 Ft LCO 3.9.4 One RHR loop shall be OPERABLE and in operation.

- NOTE -

I`N T R 0 173 VT The required RHR loop may be removed from operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that would ctause -

I tsi T* the Reactor Coolant System (RCS) boron concentration.

APPLICABILITY: MODE 6 with the water level > 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements A.1 Suspe-T Opetions* Immediately not met. "vo vin aredut4on in'RC bonconce r tratio0.9 7 AND

, S " 4 A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

AND A.3 Initiate action to satisfy RHR Immediately loop requirements.

AND A.4 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

R.E. Ginna Nuclear Power Plant 3.9.4-1 Amendment1w,

RHR and Coolant Circulation - Water Level 2! 23 Ft 3.9.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE [ FREQUENCY SR 3.9.4.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant.

R.E. Ginna Nuclear Power Plant 3.9.4-2 Amendmentw

RHR and Coolant Circulation - Water Level < 23 Ft 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation - Water Level < 23 Ft LCO 3.9.5 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

APPLICABILITY: MODE 6 with the water level < 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops RHR loop(s) to OPERABLE OPERABLE. status.

OR A.2 Initiate action to establish Immediately

> 23 ft of water above the top of reactor vessel flange.

B. No RHR Ioo Immediately operation.

AND B.2 Initiate action to restore one Immediately RHR loop to operation.

AND 3.3 Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment to outside atmosphere.

R.E. Ginna Nuclear Power Plant 3.9.5-1 Amendmento(f

RHR and Coolant Circulation - Water Level < 23 Ft 3.9.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant.

SR 3.9.5.2 Verify correct breaker alignment and indicated power 7 days available to the required RHR pump that is not in operation.

R.E. Ginna Nuclear Power Plant 3.9.5-2 Amendmento",

ML092090538

Contents

Text

SUBJECT:

Enclosure:

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

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ML092090538

Text

SUBJECT:

Enclosure:

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

SUMMARY

3.0 TECHNICAL EVALUATION

4.0 REGULATORY EVALUATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 REFERENCES

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