ML12115A307

R. E. Ginna Nuclear Power Plant - License Amendment Request for Alternate Rod Position Monitoring

ML12115A307
Person / Time
Site:	Ginna
Issue date:	04/20/2012
From:	Joseph Pacher Constellation Energy Group, EDF Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12115A307 (26)

Text

Joseph Pacher Site Vice President C E NG R.E. Ginna Nuclear Power Plant, LLC Ontario, New York 14519-9364 a joint venture of 585.771.5200 585.771.3943 Fax V

0 Consteldlatkmn *PgmeFl rl Enefv joseph.pacher*,cenqllc.com April 20, 2012 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

R.E. Ginna Nuclear Power Plant Docket No. 50-244 License Amendment Request for Alternate Rod Position Monitoring 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 actions of Technical Specification 3.1.7 requiring monitoring of inoperable control rod position indication to provide an additional monitoring option.

The proposed changes would allow monitoring of control rod drive stationary gripper coil current as an alternate to operating the incore flux monitoring equipment every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. 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.

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 safety of the public. A copy of this letter with attachments has been provided to the appropriate state representative per 1 OCFR50.91 (b)(1).

Ginna LLC requests approval of the proposed license amendment by May 1, 2013. Based on a recent rod position indicator failure, Ginna LLC recognizes the vulnerability of frequent operation of the incore monitoring system. If such a failure were to recur and repairs could not be completed online, expedited approval may be requested. Once approved, the amendment shall be implemented within 30 days.

Document Control Desk April 20, 2012 Page 2 Attachment (1) provides an evaluation of the proposed change. Attachment (2) provides the existing TS pages markup up to show the proposed change. Attachment (3) provides the re-typed TS pages to show the proposed change. No new regulatory commitments are identified in this correspondence.

Should you have questions regarding this matter, please contact Mr. Thomas Harding at (585) 771-5219 or Thomas.HardingJr@cengllc.com.

V~ej truly yours 4seph E. Pacher Attachments: (1) Evaluation of the Proposed Change (2) Proposed Technical Specification Change (Markup)

(3) Proposed Technical specification Change (Re-Typed) cc: W.M. Dean, NRC M.C. Thadani, NRC Resident Inspector, NRC (Ginna)

A. Peterson, NYSERDA

1 Document Control Desk April 20, 2012 Page 3 STATE OF NEW YORK:

TO WIT:

COUNTY OF WAYNE:

I, Joseph E. Pacher, being duly sworn, state that I am Vice President, 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. A,

-ýA Subscribed and sworn before me, a Notary Public in for the State of New York and County ofIVO(/2 0~ ,this 2 0 day of & r-'-r /2012.

WITNESS my Hand and Notarial Seal:

Notary Pubfic SHARON L.MILLER -.

Notary Public, State of New York My Commission Expires: Registration No. 01MI6017755 Monroe County ,

Commission Expires Decernber , , "

YQ10 1./

'I 1 ATTACHMENT (1)

Evaluation of the Proposed Change

N 4 Attachment 1 Evaluation of the Proposed Change TABLE OF CONTENTS 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

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

S

6.0 REFERENCES

Attachment 2 - Proposed Technical Specification Change (Markup)

Attachment 3 - Proposed Technical Specification Change (Re-Typed)

R.E Ginna Nuclear Power Plant April 20, 2012

1.0

SUMMARY

DESCRIPTION This evaluation supports a request by R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) to amend Operating License DPR-18 for the R.E. Ginna Nuclear Power Plant (Ginna).

The proposed change would revise Technical Specification (TS) 3.1.7, "Rod Position Indication". In the event that a single rod position indicator is inoperable, Action A.1 of TS 3.1.7 requires the verification of rod position by use of the movable incore detectors every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. This amendment request proposes a revision to allow the position of the rod to be monitored by a means other than movable incore detectors. Specifically, monitoring of the control rod drive gripper coil current will confirm rod position has not changed once verified by the movable incore detectors. This change would minimize excessive use and wear on the movable incore detector system. The alternate monitoring would be effective until repair of the indication system can be completed, but not longer than one operating cycle.

2.0 DETAILED DESCRIPTION The proposed change to TS 3.1.7 will add new actions that allow the use of an alternative rod position monitoring method. Action A.3.1 and A.3.2 will be incorporated to provide for the alternative monitoring. The new requirements are as follows:

Action A.3.1 Verify the position of the non-indicating rod indirectly by using the movable incore detectors.

A.3.1 Completion Time:

Once within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of condition entry (or rod control system indication of potential rod movement) and every 31 days thereafter Action A.3.2 Review the parameters of the rod control system for indications of rod movement for the rod with an inoperable position indicator.

A.3.2 Completion Time Once within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter 2

I -

A Note is added that will apply to the new Actions A.3.1 and A.3.2. This note describes the limitations for use of these new provisions. The following is the wording of the note:

Rod position monitoring by Actions A.3.1 and A.3.2 may be applied to only one inoperable rod position indicator and shall only be allowed until an entry into MODE 5 This ensures that the alternate monitoring may be in place for one inoperable indicator at most one refueling cycle or when the plant enters Mode 5 for a forced outage, whichever comes first.

The proposed change will provide an alternative to the use of the movable incore detectors every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for an extended period of time until repairs can be completed. Continued implementation of TS 3.1.7 Action A.1 would result in at least 90 operations of the incore detector system per month and may result in excessive wear on the system. Although wear of the incore detector system does not pose a significant reduction in the margin of safety, excessive wear could result in a loss of system functionality. This could lead to the inability to complete required surveillances, which could lead to a required plant power reduction and/or shutdown. This vulnerability has been recognized at Ginna based on actual Rod Position Indication concerns and alternate solutions have been reviewed based on prior industry efforts.

The marked up copy of the Technical Specification is provided in Attachment 2 and a re-typed version is provided in Attachment 3.

3.0 TECHNICAL EVALUATION

TS 3.1.7 ensures the rod position indicators are capable of determining the position of the control or shutdown rods. Mechanical or electrical failures may cause a control rod to become inoperable or to become misaligned from its group. Control rod inoperability or misalignment may cause increased power peaking due to the asymmetric reactivity distribution and a reduction in the total available rod worth for reactor shutdown. Therefore, control rod alignment and operability are related to core operation in design power peaking limits and the core design requirement of a minimum shutdown margin (SDM). Limits on control rod alignment and operability have been established, and all rod positions are monitored and controlled during power operation to ensure that the power distribution and reactivity limits defined by the design power peaking and SDM limits are preserved.

The axial position of control or shutdown rods is indicated by two separate and independent systems: the Bank Demand Position Indication System (commonly called group step counters) and the Microprocessor Rod Position Indication (MRPI) System. The Bank Demand Position Indication System counts the pulses 3

from the Rod Control System that move the rods. There is one step counter for each group of rods. Individual rods in a group all receive the same signal to move and should all be at the same position indicated by the group step counter for that group. The Bank Demand Position Indication System is considered highly precise (+/- 1 step or +/- 5/8 inch).

The MRPI System provides a highly accurate indication of actual control rod position, but at a lower precision than the step counters. The MRPI system consists of one digital detector assembly per rod. All the detector assemblies consist of one coil stack which is multiplexed and becomes input to two redundant MRPI signal processors. Each signal processor independently monitors all rods and senses a rod bottom for any rod. The MRPI system directly senses rod position in intervals of 12 steps for each rod. The digital detector assemblies consist of 20 discrete coil pairs spaced at 12-step intervals. The true rod position is always within +/- 8 steps of the indicated position (+/- 6 steps due to the 12-step interval and +/- 2 steps transition uncertainty due to processing and coil sensitivity). With an indicated deviation of 12 steps between the group step counter and MRPI, the maximum deviation between actual rod position and the demand position would be 20 steps, or 12.5 inches.

Operators use the MRPI system to monitor the position of the rods to establish that the plant is operating within the bounds of the accident analysis. Power peaking, ejected rod worth, or SDM limits may be violated in the event of a Design Basis Accident with control or shutdown rods operating outside their limits undetected. Design, Limitations, and Operation of the Rod Position Indication System are discussed in the following sections of the Updated Final Safety Analysis Report (UFSAR) 4.3, "Reload Core Nuclear Design" 7.7, "Control Systems Not Required for Safety" 15.0, "Accident Analysis" Should a technical problem arise with MRPI components inside containment, limited actions can be taken while the unit is operating. This is due to the adverse radiological and temperature environment that exists near the reactor head area.

Repairs to the MRPI coils requires removal of the shroud and shield assembly that provides a duct system for the control rod drive mechanism cooling air flow.

Inspection access doors are provided, however repair of the MRPI coil cannot be performed with the head assembly package in place. Repairs cannot be performed safely until the unit is in cold shutdown conditions (MODE 5). While troubleshooting and limited repairs can be performed in MODES 1 - 4, these are not encompassing of all credible failure modes.

Ginna considers the proposed monitoring of the status of the stationary gripper coil to be a valid means of monitoring the position of a rod once the position is confirmed through the use of the moveable incore detectors. Ginna plans to 4

monitor the coil until the unit enters Mode 5 and repairs to the system can be safety implemented. The monitoring of the position in this manner also has an added benefit that it will alleviate a concern regarding the potential for excessive wear of the incore monitoring system due to the use of the incore detectors every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to comply with Action A. 1 of TS 3.1.7.

In evaluating the requested change, the following operational events impacted by rod drop or rod misalignment were considered:

• Rod Drop or Rod Misalignment During Power Operations

• Rod Drop or Rod Misalignment During Reactor Startup

• Reactor Trip

• Shutdown Margin Rod Drop or Rod Misalignment During Power Operation A full rod drop of a control or shutdown rod will be immediately detectable by means other than the position indication system. Independent indication of a dropped rod is obtained by using the excore power range signals. This rod drop detection circuit is actuated when a rapid decrease in the local neutron flux is sensed in any of the four channels. The circuitry is designed to accommodate normal load variations in order to avoid spurious actuation. Furthermore, a negative reactivity insertion corresponding to the reactivity worth of a full rod drop will cause a noticeable change in core parameters including core power and core average temperature.

A rod misalignment may also be detectable by other measure such as axial flux difference, channel deviation, and rod control stationary regulation failure detection alarms. Based on these factors, operator actions will be initiated which are not dependent on the status of the individual rod position indication system.

For the infrequent instances when control rod bank movement is required during power operation, a determination of rod position will be made by using the movable incore detector system in accordance with plant procedures.

Considering the available indications and alarms, the increase in the likelihood of an undetected rod drop or misalignment is considered to be negligible while the alternate monitoring is used in conjunction with the other available rod drop and misalignment parameter indications.

5

Rod Drop or Rod Misalignment During Reactor Startup For a situation where there is an unplanned outage that does not result in an entry into Mode 5 and repairs are not possible in a higher Mode, Ginna plans to use the alternate monitoring. Since the movable incore detectors cannot be used to determine rod position until sometime after entry into Mode 2 when neutron flux becomes adequate, the alternate method may be used to verify that the rod is fully withdrawn, by monitoring CRDM traces. Rod position verification using this method will permit startup and entry into Mode 2. As a second diverse check, the movable incore detectors will be used to verify rod position when neutron flux becomes adequate. Following verification that the rod is withdrawn, a rod misalignment would be detectable by means other than the MRPI system (CRDM trace monitoring, axial flux difference, channel deviation, and rod control stationary regulation failure alarms). The required operator actions would not be dependent on the status of the individual rod position indication from MRPI.

Therefore, the increase in the likelihood of an undetected rod drop or misalignment during reactor startup is considered to be negligible.

Reactor Trip Following a reactor trip, the position indication system is used to verify that all rods have fully inserted. Boration is required if one or more rods fails to fully insert. If it cannot be verified with MRPI indication that all rods are on the bottom, then procedure ES-0.1, "Reactor Trip Response", currently requires boration to account for each rod not fully inserted.

Shutdown Margin Shutdown Margin in Modes 1 and 2 with Keff > 1.0 is ensured by verifying that control bank and shutdown bank rods are within limits specified in the Core Operating Limits Report (COLR). The rod insertion limit circuit is designed to provide a continuously calculated insertion limit for each of the control banks that is variable with power. It provides alarms to ensure that the operator keeps the control rods located within the limits. The rod insertion limit circuit performs its function by receiving control bank position data from the rod control system. It compares this data to the calculated limit that is determined by reactor power as measured from the coolant loop average differential temperature (delta T). The rod insertion limits ensure that adequate shutdown margin exists to shut down the reactor at any time and condition in the life of the core. The rod insertion limit monitoring circuit is independent of the rod position indication circuit. Inoperability of the rod position indication has no impact on the rod insertion limit monitoring and therefore has no impact on the ability of operators to verify Shutdown Margin. The proposed alternate method to monitor the stationary gripper coil for a control rod with an inoperable rod position indicator will provide assurance that the position has not changed and remained within the allowed misalignment with 6

the group step counter demand position for the affected control rod and the control rod bank insertion limits of TS 3.1.5 and 3.1.6.

Shutdown Margin in Mode 2 with Keff < 1 and Modes 3, 4, and 5 is determined in accordance with TS 3.1.1 by comparing the RCS boron concentration to a shutdown margin requirement curve that was generated by taking into account estimated RCS boron concentrations, core power defect, control bank position, RCS average temperature, fuel burnup based on gross thermal energy generation, xenon concentration, samarium concentration, and isothermal temperature coefficient. While in these Modes, the MRPI system is relied upon to determine rod position. While a single rod position indicator remains out of service, rod position cannot be easily determined. Accordingly, the RCS boron concentration requirements will be increased to consider an allowance for the withdrawn worth of a control rod with an inoperable position indicator. Procedure ES-0.1 currently requires boration to account for any rod that cannot be verified to be fully inserted. Shutdown Margin Calculations performed in procedures 0-3, "Hot Shutdown with Xenon Present" and 0-3.1, "Boron Concentration for the Xenon Free All Rods In - Most Reactive Rod Stuck Out Shutdown Margin" will require revision to account for the rod with inoperable indication in addition to the most reactive rod assumed to be fully withdrawn.

Adequacy of the Proposed Monitorinq The parameter monitored for a control rod or shutdown rod with an inoperable position indicator will be the stationary gripper coil current. The control rods are held in place by energized stationary gripper coils. The control rod cannot be moved without de-energizing the stationary gripper coil. The rod control power cabinet uses a resistor to monitor coil current. The gripper coil current (measured as an equivalent voltage) will be monitored on a temporary digital recorder located next to the rod control cabinet. This will allow for trending and historical data retrieval. A deviation between the actual current and the reference current will result in an Urgent Alarm signal sent to the logic cabinet and the control room annunciator. The monitored points are the same as those currently monitored by the rod control drive regulation failure detector circuit.

Since the monitoring will be performed by Operations, Ginna proposed to continue the monitoring to determine if the coils have changed state on a once every 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> basis. Should the parameters of the coils of the monitored rod indicate movement, a determination of the position of the rod will be made using the movable incore detectors within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. This timeframe is consistent with existing TS 3.1.7 Action A.1. Since verification with incore detectors is performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, continued monitoring of rod control system parameters is not required until 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> after rod movement is identified. In practice, this would occur 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after verification is performed with movable incore detectors.

7

To provide a verification of the reliability of the alternate monitoring, rod position is verified by moveable incore monitoring every 31 days. This frequency minimizes use of the movable incore monitoring system and can be performed concurrently with existing surveillance requirements for Hot Channel Factors.

A note has been added to TS 3.1.7 to ensure that the alternate monitoring requirements are not used as a long term means of verifying rod position. The intended use of this alternate is to allow for monitoring until the plant enters Mode 5 and repair of the MRPI indication can be safety performed. This ensures that at most, the alternate is used for 18 months or one operating cycle.

Compliance with either Action A. 1 or the proposed Action A.3 will result in the verification of the position of the affected rod within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by use of the movable incore detectors. Based on available information, the monitoring of the stationary gripper coil of the CRDM on the non-indicating rod as defined in proposed action A.3 will be initiated.

Impact on Indication and Alarms The following table provides a summary of the indications and alarms and how they are affected by the inoperable RPI for a control rod or shutdown rod.

Function Indication / Normal Operation Affected by Modified Alarm Operation Microprocessor MRPI Panel Provides digital rod This indication will be Based Rod position reading for unavailable and considered Position control rod or shutdown out-of-service for the control Indicator rod rod or shutdown rod with the inoperable position indication Rod Bottom MRPI Panel Provides digital This indication will be Indication indication that all rods unavailable and considered are on the bottom out-of-service for the control rod or shutdown rod with the inoperable position indication Rod Bottom / Annunciator This annunciation is The ability of the control rod Rod Drop Window C- actuated when any or shutdown rod to actuate Annunciation 14 - Rod shutdown bank rod is this annunciation will be Bottom within 8 steps to the disabled. All other control bottom of the core or rods or shutdown rods with when a control bank operable indicators will rod is within 8 steps of actuate this annunciator.

rod bottom while the remainder of the bank is greater than 31 steps above core bottom.

Rod Deviation Annunciator This annunciation is This indication is driven by Annunciation C PPCS actuated with a rod the control rod drive system Rod exceeds 12 steps from and is therefore unaffected Sequence or bank position or the by the inoperable rod 8

Rod rods are moving out of position indicator.

Deviation normal bank overlap sequence.

Rod Insertion Annunciator This annunciation is This indication is driven by Limit Monitor Windows: actuated for any control the control rod drive system C-7, 8, 15, rod bank at or below and is therefore unaffected 16, 23, 24, the limits calculated by by the inoperable rod 31, 21 - Low the rod insertion limit position indicator.

Limit and circuit.

Low-low Limit Rod Trouble Annunciator This annunciation is This indication is driven by Indication Window C- actuated for any the control rod drive system 30 condition that prevents and is therefore unaffected proper rod motion or is by the inoperable rod indicative of potentially position indicator. This undesirable rod motion. annunciator is used in conjunction with the local alternate monitor to identify unintended rod motion. Any CRDM coil current that does not match demand will cause this alarm.

Compensatory Measures To compensate for unavailable indication, the alternate monitoring system will record stationary gripper coil current. Since verification with the incore movable detector system is required within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of any rod motion, this provides a level of assurance greater than or equal to existing TS 3.1.7 action A.1.

Site procedures provide the option to also monitor lift coil current. While this option does not impact proposed Technical Specification Required Actions, this option provides additional information for verification of rod steps, which can be used during startup prior to use of the incore detectors.

Rod movement of > 24 steps since the last determination of rod position is a separate entry condition of TS 3.1.7. Required Action B.1 requires verification of position of rods with inoperable position indicators using movable incore detectors within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if rod movement of > 24 steps in one direction has been performed since the last determination of rod position. If this cannot be performed, then Required Action B.2 states that Thermal Power must be reduced to < 50% Rated Thermal Power. This condition and required actions remain unaffected by the alternate indication.

9

UL,

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements / Criteria The objectives of the rod control system and rod position indication system are to ensure that control rod alignment and insertion limits are maintained. Operators use the MRPI system as well as Rod Control System indications to monitor the positions of the rods and to establish that the plant is operating within the bounds of the accident analysis assumptions. Maximum rod misalignment is an initial condition assumption in the accident analysis.

General Design Criterion (GDC) 13 in Title 10 of the Code of Federal Regulations Part 50, Appendix A, specifies that instrumentation shall be provided to monitor variables and systems over their operating ranges during normal operation, anticipated operation occurrences, and accident conditions. Ginna TS 3.1.7 requires operability of the shutdown and control rod Position Indication system and bank demand position indication systems, and thereby provides additional measures to ensure compliance with the control rod alignment and insertion limits. The proposed alternative monitoring maintains compliance with GDC 13.

4.2 Precedents The proposed change is similar to changes approved for Sequoyah Units 1 and 2, and Turkey Point Units 3 and 4. Sequoyah submitted an amendment request on July 6, 2006 (Ref. 6.1) and was approved by the NRC on December 11, 2006 (Ref 6.2). Turkey Point submitted on November 12, 2007 (Ref. 6.3) and was approved by the NRC on January 28, 2008 (Ref. 6.4).

4.3 Significant Hazards Consideration Ginna 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 proposed change provides an alternative method for verifying rod position of one rod. The proposed change meets the intent of 10

the current specification in that it ensures verification of position of the rod once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The proposed change provides only an alternative method of monitoring rod position and does not change the assumptions or results of any previously evaluated accident.

Therefore, operation of the facility in accordance with the proposed amendment would 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.

The proposed change provides only an alternative method of determining the position of one rod. No new accident initiators are introduced by the proposed alternative manner of performing rod position verification. The proposed change does not affect the reactor protection system. Hence, no new failure modes are created that would cause a new or different kind of accidents from any accident previously evaluated. Therefore, operation of the facility in accordance with the proposed amendments would not create the possibility of a new or different kind of accident from any previously evaluated.

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

Response: No.

The basis of TS 3.1.7 states that the operability of the rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. The proposed change does not alter the requirement to determine rod position but provides an alternative method for determining the position of the affected rod. As a result, the initial conditions of the accident analysis are preserved and the consequences of previously analyzed accidents are unaffected.

Therefore, operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

Based on the above, Ginna concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

11

4.4 Conclusions Ginna LLC concludes, 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.

5.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment changes requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The proposed amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite, and no significant increase in individual or cumulative occupational radiation exposure. Ginna LLC review concluded that the proposed amendment involves no significant hazards consideration and 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

6.1 Sequoyah Nuclear Plant (SQN) Units 1 and 2 - Technical Specifications (TS) Change 06-04, Monitoring of Control or Shutdown Rod Position By An Alternate Means", July 6, 2006 6.2 Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendment Regarding Alternate Rod Position Monitoring Method, December 11, 2006, (TAC NOS. MD2514 AND MD2515) (TS-06-04) 6.3 Turkey Point Unit 4 Proposed License Amendment, "Inoperable Rod Position Indication", November 12, 2007 6.4 Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Technical Specifications 3.1.3.2, "Position Indicating Systems -

Operating" to allow for the use of an alternate method to monitor rod position for a rod with an inoperable analog rod position indication, January 28, 2008, (TAC No. MD7349 and MD7350) 12

' L t ATTACHMENT (2)

Proposed Technical Specification Change (Markup)

Attachment 2 Page 1 of 4 Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Microprocessor Rod Position Indication (MRPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODE 1, MODE 2 with Keff _>1.0.

ACTIONS

- NOTE -

Separate Condition entry is allowed for each inoperable MRPI per group and each demand position indicator per bank.

CONDITION REQUIRED ACTION COMPLETION TIME A. One MRPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or rods with inoperable more groups. position indicators by using movable incore detectors.

O._R I A.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to

• 50% RTP.

B. One or more rods with B.1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable position rods with inoperable indicators have been position indicators by using moved > 24 steps in one movable incore detectors.

direction since the last determination of the rod's OR position.

B.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to *50% RTP.

R.E. Ginna Nuclear Power Plant 3.1.7-1 Amendmeno

Attachment 2 Page 2 of 4 Insert A:

Required Action Completion Time OR Note: Rod position monitoring by Actions A.3.1 and A.3.2 may be applied to only one inoperable rod position indicator and shall only be allowed until an entry into MODE 5 A.3.1 Verify the position of the non-indicating Once within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of condition entry (OR rod rod indirectly by using the movable incore control system indication of potential rod detectors. movement) AND every 31 days thereafter AND A.3.2 Review the parameters of the rod control Once within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter system for indications of rod movement for the rod with an inoperable position indicator.

.. 1L Attachment 2 Page 3 of 4 Rod Position Indication 3.1.7 CONDITION REQUIRED ACTION COMPLETION TIME C. One demand position C.1.1 Verify by administrative Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicator per bank means all MRPIs for the inoperable for one or affected banks are more banks. OPERABLE.

AND C.1 .2 Verify the most withdrawn Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rod and the least withdrawn rod of the affected banks are < 12 steps from the OPERABLE demand position indicator for that bank.

OR C.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to *50% RTP.

D. Required Action and D.1 Be in MODE 2 with Keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time of Condition A, Condition B or Condition C not met.

E. More than one MRPI per E.1 Enter LCO 3.0.3. Immediately group inoperable for one or more groups.

OR More than one demand position indicator per bank inoperable for one or more banks.

R.E. Ginna Nuclear Power Plant 3.1.7-2 Amendmee

Attachment 2 Page 4 of 4 Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each MRPI agrees within 12 steps of the group Prior to reactor demand position for the full indicated range of rod criticality after each travel, removal of the reactor head R.E. Ginna Nuclear Power Plant 3.1.7-3 Amendmeno

ATTACHMENT (3)

Proposed Technical Specification Change (Re-Typed)

Attachment 3 Page 1 of 4 Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Microprocessor Rod Position Indication (MRPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODE 1, MODE 2 with Keff >_1.0.

ACTIONS

- NOTE -

Separate Condition entry is allowed for each inoperable MRPI per group and each demand position indicator per bank.

CONDITION REQUIRED ACTION COMPLETION TIME A. One MRPI per group A. 1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or rods with inoperable more groups. position indicators by using movable incore detectors.

OR A.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to *50% RTP.

I OR R.E. Ginna Nuclear Power Plant 3.1.7-1 Amendment XX

Attachment 3 Page 2 of 4 Rod Position Indication 3.1.7 CONDITION REQUIRED ACTION COMPLETION TIME

- NOTE -

Rod position monitoring by Actions A.3.1 and A.3.2 may be applied to only one inoperable rod position indicator and shall only be allowed until an entry into MODE 5 A.3.1 Verify the position of the Once within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> non-indicating rod indirectly of condition entry by using movable incore (OR rod control detectors. system indication of potential rod movement) AND every 31 days thereafter I AND A.3.2 Review the parameters of Once within 16 the rod control system for hours and every 8 indications of rod movement hours thereafter.

for the rod with an inoperable position indicator.

B. One or more rods with B. 1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable position rods with inoperable indicators have been position indicators by using moved > 24 steps in one movable incore detectors.

direction since the last determination of the rod's OR position.

B.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to

• 50% RTP.

R.E. Ginna Nuclear Power Plant 3.1.7-2 Amendment XX

Attachment 3 Page 3 of 4 Rod Position Indication 3.1.7 CONDITION REQUIRED ACTION COMPLETION TIME C. One demand position C.1.1 Verify by administrative Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> indicator per bank means all MRPIs for the inoperable for one or affected banks are more banks. OPERABLE.

AND C.1.2 Verify the most withdrawn Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rod and the least withdrawn rod of the affected banks are < 12 steps from the OPERABLE demand position indicator for that bank.

OR C.2 Reduce THERMAL POWER 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to

• 50% RTP.

D. Required Action and D.1 Be in MODE 2 with Keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time of Condition A, Condition B or Condition C not met.

E. More than one MRPI per E.1 Enter LCO 3.0.3. Immediately group inoperable for one or more groups.

OR More than one demand position indicator per bank inoperable for one or more banks.

R.E. Ginna Nuclear Power Plant 3.1.7-3 Amendment XX

Attachment 3 Page 4 of 4 Rod Position Indication 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each MRPI agrees within 12 steps of the group Prior to reactor demand position for the full indicated range of rod criticality after each travel, removal of the reactor head R.E. Ginna Nuclear Power Plant 3.1.7-4 Amendment XX