Text

R. E. Ginna - License Amendment 112 Technical Specification Task Force (TSTF)-286, Operations Involving Positive Reactivity Additions
	ML110980569
Person / Time
Site:	Ginna
Issue date:	06/08/2011
From:	Pickett D; Plant Licensing Branch 1
To:	John Carlin; Ginna
	Pickett D NRR/DORLLPL1-1 415-1364
References
	TAC ME5444
	Download: ML110980569 (59)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 June 8, 2011 Mr. John T. Carlin Vice President RE. Ginna Nuclear Power Plant R E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

RE. GINNA NUCLEAR POWER PLANT - AMENDMENT RE: TECHNICAL SPECIFICATION TASK FORCE (TSTF)-286, "OPERATIONS INVOLVING POSITIVE REACTIVITY ADDITIONS" (TAC NO. ME5444)

Dear Mr. Carlin:

The Commission has issued the enclosed Amendment No. 112 to Renewed Facility Operating License No. DPR-18 for the R E. Ginna Nuclear Power Plant. This amendment is in response to your application dated July 23, 2009, as supplemented by letter dated May 3, 2011.

The amendment revises Technical Specification actions requiring suspension of operations involving positive reactivity addition and revises various notes precluding reduction in boron concentration. The amendment is consistent with Technical Specification Task Force (TSTF)-286, Revision 2, Define "Operations Involving Positive Reactivity Additions."

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosures:

1. Amendment No. 112 to Renewed License No. DPR-18

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 R.E. GINNA NUCLEAR POWER PLANT, LLC DOCKET NO. 50-244 R.E. GINNA NUCLEAR POWER PLANT AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 112 Renewed License No. DPR-18

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A. The application for amendment filed by the R.E. Ginna Nuclear Power Plant, LLC (the licensee) dated July 23,2009, as supplemented on May 3,2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-18 is hereby amended to read as follows:

-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 112, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical Specifications Date of Issuance: June 8, 2011

AITACHMENT TO LICENSE AMENDMENT NO. 112 RENEWED FACILITY OPERATING LICENSE NO. DPR-18 DOCKET NO. 50-244 Replace the following page of the Facility Operating License with the attached revised page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove 3 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove 3.3.1-1 3.3.1-1 3.3.1-2 3.3.1-2 3.3.1-3 3.3.1-3 3.3.1-4 3.3.1-4 3.3.1-5 3.3.1-5 3.3.1-6 3.3.1-6 3.3.1-7 3.3.1-7 3.3.1-8 3.3.1-8 3.3.1-9 3.3.1-9 3.3.1-10 3.3.1-10 3.3.1-11 3.3.1-11 3.3.1-12 3.3.1-12 3.3.1-13 3.3.1-13 3.3.1-14 3.3.1-14 3.3.1.15 3.3.1-15 3.3.1-16 3.3.1-16 3.3.1-17 3.4.5-1 3.4.5-1 3.4.5-2 3.4.5-2 3.4.6-1 3.4.6-1 3.4.6-2 3.4.6-2 3.4.7-1 3.4.7-1 3.4.7-2 3.4.7-2 3.4.8-1 3.4.8-1 3.4.8-2 3.4.8-2 3.8.2-1 3.8.2-1 3.8.2-2 3.8.2-2 3.8.2-3 3.8.2-3 3.8.5-1 3.8.5-1

-2 Remove 3.8.5-2 3.8.5-2 3.8.8-1 3.8.8-1 3.8.8-2 3.8.8-2 3.8.10-1 3.8.10-1 3.8.10-2 3.8.10-2 3.9.2-1 3.9.2-1 3.9.2-2 3.9.2-2 3.9.4-1 3.9.4-1 3.9.4-2 3.9.4-2 3.9.5-1 3.9.5-1 3.9.5-2 3.9.5-2

- 3 (b) Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20, 1979), as supplemented February 20,1980, and March 5, 1980; (3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

(1) Maximum Power Level Ginna LLC is authorized to operate the facility at steady-state power levels up to a maximum of 1775 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 112, are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Fire Protection (a) The licensee shall implement and maintain in effect all fire protection features described in the licensee's submittals referenced in and as approved or modified by the NRC's Fire Protection Safety Evaluation (SE) dated February 14, 1979, and Amendment No. 112

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 Amendment 112

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required 0.1 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 E. As required 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 A.1 and referenced to < 5E-11 amps.

by Table 3.3.1-1.

OR E.2

- NOTE Required Action 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 8% RTP.

F. As required by Required F.1 Open 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 R.E. Ginna Nuclear Power Plant 3.3.1-2 Amendment 112

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME F.2 Immediately

- NOTE-Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations 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.

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.

AND H.2 Immediately

- NOTE-Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SDM.

Suspend operations involving positive reactivity additions.

AND R.E. Ginna Nuclear Power Plant 3.3.1-3 Amendment 112

RTS Instrumentation 3.3.1 CONDITION TIME i H .3 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OPERABLE status.

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

Time of Condition H not met. ~

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 Immediately Action A 1 and referenced -----------------

NOTE by Table 3.3.1-1.

Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SDM.

Suspend operations involving positive reactivity additions.

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 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 upto 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 Amendment 112

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME 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 Knot met.

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

- NOTE-by Table 3.3.1-1.

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 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.

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

Time of Condition M or N not met.

P. As required by Required P.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 O. Required Action and 0.1 Reduce THERMAL POWER 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Associated Completion to < 50% RTP.

Time of Condition P not met. AND R.E. Ginna Nuclear Power Plant 3.3.1-5 Amendment 112

RTS Instrumentation 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME 0.2.1 Verify Steam Dump System 7hours is OPERABLE.

OR 0.2.2 Reduce THERMAL POWER 17 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months to.< 8% RTP.

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

- NOTE-by Table 3.3.1-1.

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 hours 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.

I 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 3.3.1-6 Amendment 112

RT8 Instrumentation 3.3.1 CONDITION REQUIRED T. As required by Required T.1 Action A.1 and referenced -----------------

- NOTE by Table 3.3.1-1.

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, 8, 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 I 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 3.3.1-7 Amendment 112

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 I FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 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;:;: 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 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 ofthe incore detector measurements 31 effective full to NIS AFD and adjust if absolute difference is ;:;: 3%. power days (EFPD)

R.E. Ginna Nuclear Power Plant 3.3.1-8 Amendment 112

RTS Instrumentation 3.3.1 SURVEILLANCE SR 3.3.1.4 Perform TADOT. *31 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a STAGGERED TEST BASIS SR 3.3.1.6 ------~--------------------------*I

-NOTE-

Not required to be performed until 7 days after THERMAL POWER is?: 50% RTP, but prior to exceeding 90% RTP following each refueling.

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

SR 3.3.1.7 NOTE-Not required to be performed for source range instrumentation prior to enterin.g MODE 3 from MODE I 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 SR 3.3.1.8 ---------------------------------*1

- NOTE

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 SR 3.3.1.9 - NOTE-Setpoint verification is not required.

Perform TADOT.

R.E. Ginna Nuclear Power Plant 3.3.1-9 Amendment 112

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.10 - NOTE Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.11 Perform TADOT. 24 months SR 3.3.1.12 - NOTE Setpoint verification is not required.

Perform TADOT. Prior to reactor startup if not performed within previous 31 days R.E. Ginna Nuclear Power Plant 3.3.1-10 Amendment 112

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 SR3.3.1.11 NA 3(b), 4(b), 5(b)

2. Power Range Neutron Flux

a. High 1,2 4 D,G SR3.3.1.1 109.27%

SR331.2 RTP SR3.3.1.7 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 33.11 (d)

Neutron Flux SR 3.3.1.8 SR 3.3.1.10

4. Source Range 2(8) 2 F,G SR3.3.1.1 (d)

Neutron Flux SR 3.3,1.8 SR 3.3.1.10 3(b), 4(b), 5(b) 2 H,I SR 3.3.1.1 (d)

SR 3.3.17 SR3,3.1.10 3(f), 4(1),5(1) J SR3.3.1.1 NA SR3,3.1,10

5. Overtemperature D..T 1,2 4 D,G SR3.3.1.1 Refer to SR 3.3.1.3 Note 1 SR3.31.6 SR 3.3,1.7 SR 3.3.1.10

6. Overpower D..T 1. 2 4 D,G SR 3.3 1 1 Refer to SR 3.3.1.7 Note 2 SR 3.3.1.10 Ginna Nuclear Power Plant 3.3,1-11 Amendment 112

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 SETIINGS(a)

7. Pressurizer Pressure

a. Low 1(g) 4 K,L SR 3.3.1.1 21791.3 SR3.3.1.7 psig SR 3.3.1.10

b. High 1, 2 3 D,G SR 3.3.1.1 ::; 2396.2 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 SR3.3.1.7 SR 3.3.1.10 9 Reactor Coolant Flow-Low

a. Single Loop 1(h) 3 per loop M,O SR 3.3.1.1 289.86%

SR 3.3.1.7 SR 3.3.1.10

b. Two Loops 1(i) 3 per loop K,L SR 3.3.1.1 289.86%

SR 3.3.1.7 SR 3.3.1.10

10. Reactor Coolant Pump (RCP)

Breaker Position

a. Single Loop 1(h) 1 per RCP N,O SR3.3.1.11 NA

b. Two Loops 10) 1 per RCP K,L SR 3.3.1.11 NA

11. Undervoltage- 1(g) 2 per bus K,L SR 3.3.1.9 (d)

Bus 11 A and 11 B SR 3.3.1.10

12. Underfrequency- 1(g) 2 per bus K,L SR 3.3.1.9 257.5 HZ Bus 11 A and 11 B SR 3.3.1.10 R.E. Ginna Nuclear Power Plant 3.3.1-12 Amendment 112

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 SETIINGS(a)

13. Steam Generator 1, 2 3 per SG D,G SR 3.31.1 2: 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)(l) 3 P,Q SR 3.3.1.10 (d)

Oil Pressure SR 3.3.1.12

b. Turbine Stop 1(k)(l) 2 P.Q SR3.3.1.12 NA Valve Closure

15. Safety Injection (SI) 1,2 2 R,V SR3.3.1.11 NA Input from Engineered Safety Feature Actuation System (ESFAS)

R.E. Ginna Nuclear Power Plant 3.3.1-13 Amendment 112

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)

16. Reactor Trip System Interlocks

a. Intermediate 2(e) 2 S,V SR 3.3.1.10 ~5E-11 Range SR 3.3.1.13 amp Neutron Flux, P-6

b. Low Power 1 (g) 4 (power range S.V SR 3.3.1.10 8.0% RTP Reactor Trips only) SR3.3.1.13 Block, P-7

c. Power Range 1(h) 4 S.V SR 3.3.1.10 290%

Neutron Flux, SR 3.3.1.13 RTP P-8

d. Power Range 1(I) 4 S,V SR3.3.1.10 500%

Neutron Flux, SR3.3.1.13 RTP P-9 1(k) 4 S,V SR 3.3.1.10 80% RTP SR3.3.1.13

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

17. Reactor Trip 1,2 2 trains T,V SR 3.3.14 NA Breakers(m) 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 RE. Ginna Nuclear Power Plant 3.3.1-14 Amendment 112

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:

las-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;:: 8.5% RTP and Reactor Coolant Flow-Low (Single Loop) trip Function blocked.

U) THERMAL POWER 28,5% 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 2 50% RTP, 1 of 2 Circulating water pump breakers closed, and condenser vacuum> 20".

(m) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB, R.E. Ginna Nuclear Power Plant 3.3.1-15 Amendment 112

RTS Instrumentation 3.3.1 Table 3.3.1-1 (Note 1)

Overtem perature 6.T

- NOTE-The Overtemperature tJ.T Function Limiting Safety System Setting is defined by:

Where:

tJ.T is measured RCS tJ.T, of tJ.T 0 is the indicated tJ.T at RTP, of s is the Laplace transform operator, sec- 1.

T is the measured RCS average temperature, of T' is the nominal T avg at RTP, OF P is the measured pressurizer pressure, psig.

P' is the nominal ReS operating pressure, psig.

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

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

K3 is the Overtemperature tJ.T reactor trip heatup setpoint penalty coefficient, [*]/oF 1:1 is the measured lead time constant, [*] seconds.

1:2 is the measured lag time constant, [*] seconds.

f(tJ.I) 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.

when qt - qb S [*]% RTP when [*] % RTP < qt - qb S [*]% RTP when qt - qb > [*J% RTP

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

R Ginna Nuclear Power Plant 3.3.1-16 Amendment 112

RTS Instrumentation 3.3.1 Table 3.3.1-1 (Note 2)

Overpower .0.T

- NOTE-The Overpower 11T Function Limiting Safety System Setting is defined by:

Where:

.c,T is measured RCS .c,T, of.

.c,To is the indicated .c, T at RTP, of.

s is the Laplace transform operator, sec- 1 .

T is the measured RCS average temperature, of.

l' is the nominal T avg at RTP, oF.

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

K5 is the Overpower 11T reactor trip heatup setpoint penalty coefficient which is:

[*WF for T < l' and;

[*WF for T ~ 1'.

K6 is the Overpower .c, T reactor trip thermal time delay setpoint penalty which is:

[*WF for increasing T and;

[*WF for decreasing T.

'3 is the measured impulse/lag time constant, [*] seconds.

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

R.E. Ginna Nuclear Power Plant 3.3.1-17 Amendment 112

RCS Loops MODES 1 S; 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 s; 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. 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

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 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. 112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months associated Completion Time of Condition A not met.

R.E. Ginna Nuclear Power Plant 3.4.5-1 Amendment 112

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

C.2 Suspend operations that Immediately No RCS loop in operation. would cause introduction of coolant into the RCS with boron concentration less than required to meet the SDM of LCO 3.1.1.

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 R.E. Ginna Nuclear Power Plant 3.4.5-2 Amendment 112

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 s 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. 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

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 s 50 F above each of the RCS cold leg Q

temperatures; or

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

APPLICABILITY: MODE4.

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

Two RHR loops inoperable.

R.E. Ginna Nuclear Power Plant 3.4.6-1 Amendment 112

RCS Loops - MODE 4 3.4.6 CONDITION REQUIRED ACTION COMPLETION TIME B. One RHR loop ------------------

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

Two RCS loops ------------------

inoperable, B.1 Be in MODE 5, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. All RCS and RHR loops C.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with boron concentration less than required to meet the No RCS or RHR loop in SDM ofLC03.1.1.

operation.

AND C.2 Initiate action to restore one Immediately loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify SG secondary side water level is ~ 16% for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months each required RCS loop.

SR 3.4.6.3 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

R.E. Ginna Nuclear Power Plant 3.4.6-2 Amendment 112

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 2. 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

a. 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

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 Amendment 112

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 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet the No RHR loop in SDM of LCO 3.1.1.

operation.

AND 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 Amendment 112

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. 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

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 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 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with boron concentration less than required to meet the No RHR loop in SDM of LCO 3.1.1.

operation.

lAND R.E. Ginna Nuclear Power Plant 3.4.8-1 Amend ment 112

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 REQUIREIVIENTS 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 Amendment 112

AC Sources - IVIODES 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.

APPLICABI LlTY: MODES 5 and 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Offsite power to one or

- 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 R.E. Ginna Nuclear Power Plant 3.8.2-1 Amendment 112

R.E. Ginna Nuclear Power Plant 3.8.2-2 Amendment 112 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 i 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 Amendment 112

DC Sources - MODES 5 and 6 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - MODES 5 and 6 LCO 3.8.5 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 REQUIRED ACTION COMPLETION TIME I

A. One or more required DC I A.1 Declare affected required Immediately electrical power source(s) feature(s) inoperable.

inoperable.

A.2.1 Suspend CORE Immediately ALTERATIONS.

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

AND A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

AND 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 Amendment 112

DC Sources - MODES 5 and 6 3.8.5 SURVEILLANCE REQUIREMENTS SU RVEI LLANCE FREQUENCY SR 3.8.5.1 For DC sources required to be OPERABLE, SR In accordance with 3.8.4.1 is applicable. applicable SR Ginna Nuclear Power Plant 3.8.5-2 Amendment 112

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 REQUIRED ACTION i COMPLETION TIME A. One or more required AC i 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 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SOM or boron concentration.

AND A.2.4 Initiate action to restore Immediately required AC instrument bus power source(s) to OPERABLE status.

R. Ginna Nuclear Power Plant 3.8.8-1 Amendment 112

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 112

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.

R.E. Ginna Nuclear Power Plant 3.8.10-1 Amendment 112

Distribution Systems - MODES 5 and 6 3.8.10 CONDITION REQUIRED ACTION COIVIPLETION TIIVIE A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immed iately irradiated fuel assemblies.

AND A.2.3 Suspend operations Immediately involving positive reactivity additions that could result in loss of required SDM or boron concentration.

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 Amendment 112

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' REQUIRED ACTION I COMPLETION TIME A. One sou rce range A.1 Suspend CORE ' Immediately neutron flux monitor ALTERATIONS.

inoperable.

AND A.2 Suspend operations that Immediately would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

B. Two sou rce 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.

AND RE. Ginna Nuclear Power Plant 3.9.2-1 Amendment 112

Nuclear Instrumentation 3.9.2 CONDITION REQUIRED ACTION I COMPLETION TIME C.2 Suspend positive reactivity Immediately additions.

C.3 Perform SR 3.9.1.1 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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. 112 hours0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months SR 3.9.2.2 ._------------------------------_.

- NOTE-Neutron detectors are excluded from CHANNEL CALIBRATION. *

~~~:r~~~;~~~L-~;L~~~;~~~- - - - - - - - - - - *j24 months R.E. Ginna Nuclear Power Plant 3.9.2-2 Amendment 112

RHR and Coolant Circulation Water Level 2 23 Ft 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation - Water Level 223 Ft LCO 3.9.4 One RHR loop shall be OPERABLE and in operation.

- NOTE-The required RHR loop may be removed from operation for s; 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 . .

APPLICABILITY: MODE 6 with the water level 2 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements A.1 Suspend operations that Immediately not met. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

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

R.E. Ginna Nuclear Power Plant 3.9.4-1 Amendment 112

RHR and Coolant Circulation - Water Level :2: 23 Ft 3.9.4 CONDITION REQUIRED ACTION COMPLETION TIME 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. !

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one RHR is in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor R.E. Ginna Nuclear Power Plant 3.9.4-2 Amendment 112

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

0

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

B. No RHR loop in B.1 Suspend operations that Immediately operation. would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

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

AND B.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 R.E. Ginna Nuclear Power Plant 3.9.5-1 Amendment 112

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 Amendment 112

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 112 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-18 RE. GINNA NUCLEAR POWER PLANT, LLC RE. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244

1.0 INTRODUCTION

By letter dated July 23, 2009 (Reference 1), as supplemented by letter dated May 3, 2011, (Reference 2), RE. Ginna Nuclear Power Plant, LLC (the licensee) submitted a request for changes to the RE. Ginna Nuclear Power Plant (Ginna) Technical Specifications (TSs). The proposed changes would revise the Required Actions requiring suspension of operations involving positive reactivity additions and various notes that preclude reduction in boron concentration. The proposed changes would limit the introduction of positive reactivity such that the required margin to the Shutdown Margin (SDM) and refueling boron concentration limits will be maintained. These proposed changes are similar to those proposed in the Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) change traveler TSTF-286, Revision 2. as modified by the NRC in a letter dated May 16, 2003 (Reference 3).

The letter dated May 3, 2011, provided additional information that clarified the application, did not expand the scope of the application as originally noticed. and did not change the staffs original proposed no significant hazards consideration determination as published in the FEDERAL REGISTER

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (10 CFR), 50.36, "Technical specifications,"

requires that each license operate in accordance with plant-specific TSs. 10 CFR 50.36 requires that the TSs include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.

The licensee adopted the Improved TSs in License Amendment Number 61 (Reference 4) based on NUREG-1431, "Standard Technical Specifications [STS], Westinghouse Plants,"

Revision 0, dated September 1992. Since then, industry and the NRC staff have been working

-2 to improve the STS, in NUREG-1430 through NUREG-1434 for the different plant vendors, and as a result, generic changes have been developed for the STS in NUREG-1431.

In its license amendment request, the licensee is requesting to adopt generic changes to the STS proposed by the industry in TSTF-286, Revision 2, that were approved by the NRC staff in a letter dated July 6, 2000 (Reference 5). The NRC staff's approval was subsequently modified by the NRC staff in Reference 3. It is this modified version of the approved TSTF-286, Revision 2 that is currently incorporated into the STS, and will be referred to in this safety evaluation as the approved TSTF-286. This TSTF revises Required Actions to suspend operations involving positive reactivity additions and limiting conditions for operation (LCOs) notes to prevent operations involving a reduction in reactor coolant system (RCS) boron concentration. The proposed changes limit the introduction into the RCS of reactivity more positive than that required to meet the required SOM or refueling boron concentration, as applicable. TSTF-286 provides a model for licensees seeking to revise their plant TSs and clarify limits on the introduction of reactivity such that the required SOM or refueling boron concentration will be satisfied. Proper adoption of TSTF-286 would bring the Ginna TSs into closer alignment with the STS.

10 CFR Part 50, Appendix A, General Oesign Criteria 26, "Reactivity control system redundancy and capability," requires that two independent reactivity control systems of different design principals shall be provided. The licensee employs two independent reactivity control systems.

One uses the movable control and shutdown rod cluster control assemblies (RCCAs), and the other uses the chemical and volume control system (CVCS) to adjust the soluble boron concentration in the reactor coolant system (RCS). In Modes 1 and 2, both systems are used to compensate for the reactivity effects from fuel and coolant temperature changes in the RCS during power operation from full load to a no-load condition. In Modes 3, 4, and 5, the CVCS is used to compensate for the reactivity effects from core temperature and xenon changes. In Mode 6, the CVCS is used to maintain the boron concentration within the required limits.

The Ginna SOM limit provides sufficient subcritical reactivity margin to ensure that the specified acceptable fuel design limits (SAFOLs) will not be exceeded for normal operation and anticipated operational occurrences (AOOs). The SOM definition assumes that the single Rod Cluster Control Assembly (RCCA) with the highest reactivity worth remains fully withdrawn following a reactor scram. In Modes 1 and 2, TSs 3.1.4, "Rod Group Alignment Limits," 3.1.5, "Shutdown Bank Insertion Limit," and 3.1.6, "Control Bank Insertion Limits," satisfy the required SOM by limiting the insertion of the control and shutdown rod banks. Small reactivity changes due to RCS coolant inventory management and temperature control are also considered in specifying SOM, including moderator temperature coefficient (MTC) effects. At the beginning of core life, a positive MTC coefficient must be considered as allowed by TS 3.1.3, "Moderator Temperature Coefficient (MTC)." In Mode 2 with keff < 1.0, and Modes 3, 4, and 5, the TSs specify the required SOM by reference to the Core Operating Limits Report (COLR). In Mode 6, the reactor sub-criticality margin is ensured by the limit on the boron concentration of all filled portions of the RCS, the refueling canal, and the refueling cavity that have direct access to the reactor vessel. These TSs will be modified by this amendment to permit the addition of positive reactivity and changes to the RCS boron concentration as long as the change preserves the margin to core criticality as defined by the SOM and refueling boron concentration limit specifications. The limit specifications for the SOM and refueling boron concentration are given

- 3 in TSs 3.1.1, "Shutdown Margin (SOM)," and 3.9.1, "Boron Concentration," respectively, with the limit values specified in the COLR.

The NRC has previously approved the subject change on a plant-specific basis. These previous approvals include but are not limited to H.B. Robinson Unit 2 (Reference 6),

Callaway Unit 1 (Reference 7), Wolf Creek Generating Station (Reference 8), Catawba Nuclear Station Units 1 and 2 (Reference 9), McGuire Nuclear Station Units 1 and 2 (Reference 10), and Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 (Reference 11).

3.0 TECHNICAL EVALUATION

3.1 Staff Evaluation The licensee requested a change to the TSs for Ginna to revise TS Required Actions that currently require suspending all operations involving any positive reactivity additions, and to revise TS LCO notes that preclude any reduction in boron concentration. The proposed changes would allow the introduction of reactivity as long as the TS required SOM or refueling boron concentration is properly maintained. The licensee stated that these necessary operations may involve additions to the RCS of cooler borated water or required makeup from borated sources that have lower boron concentration than the existing RCS boron concentration. The licensee indicated that these changes would be allowed if the overall effect on core reactivity still assures that the required SOM or the refueling boron concentration is maintained. The proposed changes are consistent with TSTF-286 except where noted below.

The licensee provided plant-specific differences between the proposed changes and TSTF-286 as part of its application.

TSTF-286, Revision 2, revises the following in the STS: (1) various Required Actions that require suspension of operations involving positive reactivity additions, and (2) various TS notes precluding reduction in boron concentration. The revised TSs for Ginna will limit the introduction of positive reactivity into the RCS to that which would maintain the TS required SOM or refueling boron concentrations, as applicable. The applicable TS Bases have been revised accordingly.

The justification given in the TSTF is that the change provides the flexibility necessary to provide for continued safe reactor operations while also limiting any potential for excess positive reactivity addition to the core. The Required Actions and LCO Notes that preclude positive reactivity changes and/or reduction in boron concentration ensure that either no power increases will be experienced or that continued core criticality margins will be maintained.

During conditions in which these Required Actions may be required, the following various activities for unit operation must be continued: RCS inventory must be maintained, and RCS temperature must be controlled. These activities involve addition to the RCS of cooler water and may involve inventory makeup from sources that are at boron concentrations less than the current RCS concentration, but limit the introduction of reactivity more positive than that required to meet the required SOM or boron concentration, as applicable. These activities do not need to be precluded in the TSs to ensure that, for the worst-case overall effect on the core, there would still be assurance that the required SOM is maintained.

The licensee employs two independent reactivity control systems. One uses the movable control and shutdown control rods, and the other uses the Chemical and Volume Control

- 4 System (CVCS) to adjust the soluble boron concentration in the RCS. In Modes 1 and 2, both systems are used to compensate for the reactivity effects from fuel and coolant temperature changes in the RCS during power operation from full load to no load conditions. In Modes 3, 4, and 5, the CVCS is used to compensate for reactivity effects from core temperature and reactor poisons, such as xenon. In Mode 6, the CVCS is used to maintain the boron concentration within the required limits.

In Modes 1 through 4, the minimum required SOM is assumed as an initial condition for the reload safety analyses to ensure that the SAFOLs will not be exceeded for normal operation and AOOs, assuming that the highest worth RCCA remains stuck out following a reactor scram. The main steam line break (MSLB) and boron dilution accidents are the most limiting events to establish the minimum SOM value for LCO 3.1.1 and the minimum boron concentration requirement of LCO 3.9.1, respectively. For MSLB accidents, if LCO 3.1.1 is not met, there is 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 LCO 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.

As stated in the Bases for LCO 3.1.1, a sufficient shutdown margin ensures that: (1) the reactor can be made subcritical from all operating conditions, transients, and design basis events; (2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits; and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. The Bases for LCO 3.9.1 on refueling boron concentration in the RCS, refueling canal and refueling cavity similarly indicate that the limitations on boron concentration during refueling ensure that the reactor will remain subcritical during Mode 6. Since the proposed changes will not alter the limits established in these specifications, the NRC staff concludes that the proposed changes will have no effect on the licensee's ability to shut down and maintain the reactor in a subcritical condition.

The changes specified in TSTF-286, Revision 2, ensure that, under the specified plant conditions for each operating mode, unplanned power increases or reductions in the margin to core criticality are precluded. The proposed revision to existing TS Notes and the addition of wording to the TS ACTIONS allow the small reactivity variations that result from the temperature or boron concentration fluctuations associated with normal RCS inventory management or temperature control. These normal activities are permitted to be performed while maintaining the minimum SOM requirement of LCO 3.1.1 and the minimum boron concentration requirement of LCO 3.9.1.

In the application, the licensee provided justification for changes that are consistent with TSTF 286, Revision 2. Where plant-specific design would dictate differences, the licensee provided plant-specific justification for any differences or exceptions, as discussed below. The proposed TS changes are applicable to Ginna.

(a) The proposed changes include adding notes to LCO 3.3.1, "Reactor Trip System (RTS)

Instrumentation," Required Actions F.1, H,1, and J.1.

- 5 The current Required Actions F.1 and H.1 both state the following: "Suspend operations involving positive reactivity additions." TSTF-286, Revision 2, adds equivalent notes that allow limited insertions of positive reactivity associated with routine plant operations. The notes state that "Limited plant cooldown or boron dilution is allowed provided the change is accounted for in the calculated SDM."

The current Required Action J.1 states the following: "Suspend operations involving positive reactivity additions." TSTF-286, Revision 2, adds an equivalent note that allows limited insertions of positive reactivity associated with routine plant operations. The note states that "Plant temperature changes are allowed provided the temperature change is accounted for in the calculated SDM."

As previously stated, the intent of TSTF-286 is to ensure that under the specified plant conditions for each operating mode, unplanned power increases or reductions in the margin to core criticality are precluded. The proposed addition of TS Notes will allow small reactivity effects that result from temperature or boron concentration fluctuations associated with RCS inventory management or temperature control. These routine plant operations would be permitted to be performed while maintaining the minimum SDM requirement of LCO 3.1.1. SDM is assured by operation within rod insertion limits of LCO 3.1.4, "Rod Group Alignment Limits," 3.1.5, "Shutdown Bank Insertion Limit,"

and 3.1.6, "Control Bank Insertion Limits." The addition of the TS notes continue to provide the NRC staff the assurance that the assumptions of the most limiting accident safety analyses are maintained, while acknowledging that necessary activities may still be taken by adding cooler water to the RCS to lower the current temperature and makeup sources may be borated water at concentrations less than the current RCS boron concentration.

The proposed change is acceptable because the overall effect on core reactivity is being monitored and the required SDM is being maintained. Furthermore, the NRC staff finds the wording "temperature changes" refers to the fact that the moderator temperature coefficient must be considered both during cooldown and heatup operations.

(b) The proposed changes include changes to Notes for the following LeOs:

LCO 3.4.5, "RCS Loops - MODE 1 s 8.5% rated thermal power (RTP), 2, and 3,"

Note a

LCO 3.4.6, "RCS Loops - MODE 4," Note 1.a

LCO 3.4.7, "RCS Loops - MODE 5, Loops Filled," Note 1.a

LCO 3.4.8, "RCS Loops - MODE 5, Loops Not Filled," Note 1.a The LCO Notes would be changed to state that "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." These Notes currently state: "No operations are permitted that would cause reduction of the RCS boron concentration; and." These Notes are intended to preclude dilution of the RCS when no forced mixing (i.e., coolant circulation by Residual Heat Removal (RHR) pumps or reactor coolant pumps) is taking place. The proposed changes allow dilution of the RCS, but the source of boric acid is

-6 required to contain a soluble boron concentration greater than that required to meet the SDM requirement of LCD 3.1.1. These proposed changes are consistent with the changes in the approved TSTF-286 for the same LCD notes.

The applicability of STS LCD 3.4.5 is Mode 3 while the applicability of the Ginna LCD 3.4.5 is Modes 1 S 8.5% RTP, 2, and 3. Ginna's LCD 3.4.5 Note states, "Both reactor coolant pumps may be de-energized in Mode 3 for S 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: .... >> Since Ginna's note only applies in Mode 3 it is consistent with Note a in STS LCD 3.4.5 and TSTF-286.

The licensee provided the same technical basis for these changes as that provided by the NRC staff for the approved TSTF-286. These changes are consistent with the wording of the approved TSTF-286, are applicable to Ginna, and will ensure that adequate SDM will be maintained. Therefore, the NRC staff finds the proposed changes acceptable.

(c) The proposed changes include changes to Required Actions for the following LCOs:

LCD 3.4.6, "RCS Loops - MODE 4," Required Action C.1

LCD 3.4.7, "RCS Loops - MODE 5, Loops Filled," Required Action B.1

LCD 3.4.8, "RCS Loops - MODE 5, Loops Not Filled," Required Action 8.1 The proposed changes would revise the Required Actions to state the following:

"Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCD 3.1.1." The current Required Actions states: "Suspend all operations involving a reduction of RCS boron concentration." These Required Actions are intended to preclude dilution of the RCS when no forced mixing is taking place. The proposed changes allow dilution of the RCS, but the source of boric acid is required to contain a soluble boron concentration greater than that required to meet the SDM requirement of LCD 3.1.1. These proposed changes are identical to the changes in the approved TSTF-286 for the same Required Actions.

The licensee provided the same technical basis for these changes as that provided by the NRC staff for the approved TSTF-286. These changes are identical to the wording of the approved TSTF-286, are applicable to Ginna, and will ensure that adequate SDM will be maintained. Therefore, the NRC staff finds the proposed changes acceptable.

(d) The licensee proposed the following change to Required Action C.2 for LCD 3.4.5, "RCS Loops - MODE 1 S 8.5% RTP, 2, and 3."

The proposed change would revise the Required Action to state the following:

"Suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCD 3.1.1." The current Required Action states: "Suspend all operations involving a reduction of RCS boron concentration." This Required Action is intended to preclude dilution of the RCS when no forced mixing is taking place. The proposed change allows dilution of the RCS, but

-7 the source of boric acid is required to contain a soluble boron concentration greater than that required to meet the SDM requirement of LCD 3.1.1.

The applicability of STS LCD 3.4.5 is Mode 3 while the applicability of the Ginna LCD 3.4.5 is Modes 1 :s; 8.5% RTP, 2, and 3. Ginna's LCD 3.4.5 Required Actions for Condition C require immediately (1) de-energizing all control rod drive mechanisms (CRDMs), (2) suspending all operations involving a reduction of RCS boron concentration. and (3) initiating action to restore operability and operation of one RCS loop. When Ginna de-energizes all CRDMs, keff is reduced to < 0.99 which changes reactor mode from Mode 1 to Mode 3. Since Required Action C.1 places the reactor in Mode 3, Ginna's proposed change is consistent with the Mode 3 applicability of STS LCD 3.4.5.

This proposed change is consistent with the changes in TSTF-286 for the same LCOs.

The licensee provided the same technical basis for this change as that provided by the NRC staff for the approved TSTF-286. This change is consistent with the wording of the approved TSTF-286, is applicable to Ginna. and ensures that adequate SDM will be maintained. Therefore, the NRC staff finds the proposed change acceptable.

(e) The proposed changes include changes to Required Actions for the following TSs:

LCD 3.8.2. HAC Sources - MODES 5 and 6," Required Actions A.2.3 and B.3

lCO 3.8.5. "DC Sources - MODES 5 and 6," Required Action A.2.3

lCO 3.8.8, (lAC Instrument Bus Sources - MODES 5 and 6," Required Action A.2.3

LCD 3.8.10, "Distribution Systems - MODES 5 and 6," Required Action A.2.3 The proposed Required Actions would state the following: "Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration." These Required Actions currently state: "Initiate action to suspend operations involving positive reactivity additions." These Required Actions are intended to initiate suspension of operations involving positive reactivity additions based on the loss of required electrical sources and distribution equipment. The proposed changes allow dilution of the ReS, but the source of boric acid is required to contain a soluble boron concentration greater than that required to meet the SDM requirement of LCD 3.1.1 or the refueling boron concentration of LCD 3.9.1. The proposed changes will also allow temperature changes that could increase reactivity provided the reactivity insertions do not result in a loss of required SDM. These proposed changes are identical to the changes in TSTF-286, as modified by the NRC staff, for the same Required Actions.

The licensee provided the same technical basis for these changes as that provided by the NRC staff for the approved TSTF-286. These changes are identical to the wording of the approved TSTF-286, are applicable to Ginna. and will ensure that adequate SDM is maintained. Therefore. the NRC staff finds the proposed changes acceptable.

(f) The licensee proposed the following change to Required Action A.2 for LCD 3.9.2, "Nuclear Instrumentation."

- 8 The proposed Required Action states the following: "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 Required Action currently states:

"Suspend positive reactivity additions." This Required Action is intended to initiate suspension of operations during refueling operations involving positive reactivity additions when there is a loss of one source range monitor. The proposed change allows dilution of the RCS, but the source of boric acid is required to contain a soluble boron concentration greater than that required to meet the minimum refueling boron concentration requirement of LCO 3.9.1, which ensures that inadvertent criticality will not occur. The proposed change is identical to the change in the approved TSTF-286 for this Required Action.

The licensee provided the same technical basis for this change as that provided by the NRC staff for the approved TSTF-286. The change is identical to the wording of the approved TSTF-286, is applicable to Ginna, and ensures that adequate SOM will be maintained. Therefore, the NRC staff finds the proposed change acceptable.

(g) The licensee proposed the following change to Required Action C.2 for LCO 3.9.2, "Nuclear Instrumentation."

Ginna's Updated Final Safety Analysis Report section 15.4.4.3.2 states, "The event analyses require the operator to terminate the transients by isolating the source of flow causing the boron dilution. The minimum time intervals that must be available to the operator to identify the cause and terminate the dilution before a loss of shutdown margin occurs are calculated from the time the dilution begins. The calculated time intervals must be greater than or equal to 30 min for refueling events and greater than or equal to 15 min for all other plant operating modes. The operator is then expected to re establish boron concentrations and shutdown margins required by the Technical Specifications. "

The licensee's technical evaluation states, "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 Required Action states the following: "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 Required Action currently states:

"Suspend positive reactivity additions." This Required Action is intended to initiate suspension of operations during refueling operations involving positive reactivity additions when there is a loss of audible count rate. With no audible count rate available, prompt and definite indication of a boron dilution event, consistent with the assumptions of the safety analysis, is lost. In this situation, the boron dilution event may not be detected quickly enough to assure sufficient time is available for operators to identify the cause and stop the dilution prior to the loss of shutdown margin. Therefore, action must be taken to prevent an inadvertent boron dilution event from occurring. An inadvertent boron dilution event is prevented by suspending any positive reactivity additions as currently required by Required Action C.2 for LCO 3.9.2.

- 9 Following discussions between the NRC staff and the licensee on this item, by letter dated May 3, 2011, the licensee withdrew their proposed revision to Required Action C.2 for LCO 3.9.2.

(h) The licensee proposed the following change to the note in LCO 3.9.4, "Residual Heat Removal (RHR) and Coolant Circulation - Water Level;:: 23 Ft":

The proposed LCO 3.9.4 Note would state the following: "The required RHR loop may be removed from operation for:s 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." The LCO 3.9.4 Note currently states that: 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 reduction of the Reactor Coolant System (RCS) boron concentration." The allowance of removing the required RHR loop for.:::. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8-hour period is not being changed by the proposed amendment. This note is intended to preclude dilution of the RCS when no forced mixing is taking place during refueling. The proposed change allows dilution of the RCS, but the source of boric acid is required to contain a soluble boron concentration greater than that required to meet the minimum refueling boron concentration requirement of LCO 3.9.1, which ensures that inadvertent criticality will not occur. This proposed change is identical to the change in the approved TSTF-286 for the same LCO Note.

The licensee provided the same technical basis for this change as that provided by the NRC staff for the approved TSTF-286. This proposed change is identical to the wording of the approved TSTF-286, is applicable to Ginna, and will ensure that adequate SOM is maintained. Therefore, the NRC staff finds that the proposed change acceptable.

(i) The proposed changes include changes to Required Actions for the following TSs:

LCO 3.9.4, "Residual Heat Removal (RHR) and Coolant Circulation - Water Level

23 Ft." Required Action A.1

LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - Water Level

< 23 Ft," Required Action B.1 The proposed Required Actions would state the following: "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." These Required Actions currently state: "Suspend operations involving a reduction in reactor coolant system boron concentration." These Required Actions are intended to preclude dilution of the RCS when no forced mixing is taking place during refueling. The proposed changes allow dilution of the RCS, but the source of the boric acid is required to contain a soluble boron concentration greater than that required to meet the minimum refueling boron concentration requirement of LCO 3.9.1, which ensures that inadvertent criticality will not occur. These proposed changes are identical to the changes in the approved TSTF-286 for the same Required Actions.

- 10 The licensee provided the same technical basis for these changes as that provided by the NRC staff for the approved TSTF-286. These changes are identical to the wording of the approved TSTF-286, are applicable to Ginna, and will ensure that adequate SOM is maintained. Therefore, the NRC staff finds the proposed changes acceptable.

The Ginna plant-specific adoption of TSTF-286, as modified by the NRC staff, provides the NRC staff the assurance that the initial assumptions of the most limiting accident safety analyses are still maintained, while acknowledging that necessary routine plant operations may still be taken by adding cooler water to the RCS to lower the current temperature; and makeup sources may be borated water at boron concentrations less than the current RCS boron concentration.

These routine plant operations are part of plant procedures, and this would assure that the overall effect on core reactivity is properly monitored, and the TS required SOM or the required refueling boron concentration is maintained. Therefore, the NRC staff finds the changes acceptable.

3.2 Conclusion of the NRC Staff Evaluation The NRC staff has reviewed the licensee's application with the supporting documentation.

Based on its review, the NRC staff concludes that the proposed changes to the TSs are acceptable because proposed notes and Required Actions prevent the introduction of coolant into the RCS with boron concentration less than that required to meet the required SOM or refueling boron concentration. In addition, these changes are consistent with the approved TSTF-286 which is applicable to Ginna and takes into account plant-specific design differences discussed above. The technical basis for the approved TSTF-286 is applicable to Ginna, and continues to ensure that the required minimum SOM of LCO 3.1.1 and boron concentration of LCO 3.9.1 to preclude inadvertent criticality are met. Since the licensee's proposed amendment will still require the minimum SOM and boron concentration to be maintained, the NRC staff concludes that the proposed changes below are acceptable.

Adding notes to LCO 3.3.1 Required Actions F.1, H.1, and J.1

Revising LCO 3.4.5 Note a

Revising LCO 3.4.6 Note 1.a

Revising LCO 3.4.7 Note 1.a

Revising LCO 3.4.8 Note 1.a

Revising LCO 3.4.5 Required Action C.2

Revising LCO 3.4.6 Required Action C.1

Revising LCO 3.4.7 Required Action B.1

Revising LCO 3.4.8 Required Action 8.1

Revising LCO 3.8.2 Required Actions A.2.3 and B.3

Revising LCO 3.8.5 Required Action A.2.3

Revising LCO 3.8.8 Required Action A.2.3

Revising LCO 3.8.10 Required Action A.2.3

Revising LCO 3.9.2 Required Action A.2

Revising LCO 3.9.4 Note

Revising LCO 3.9.4 Required Action A.1

Revising LCO 3.9.5 Required Action B.1

- 11

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes Surveillance Requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (76 FR 12765). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22{c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

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

7.0 REFERENCES

1. Larson, Eric A, RE. Ginna Nuclear Power Plant, LLC, to USNRC, "License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)," July 23,2009 (ADAMS Accession No. ML092090538).

2. Carlin, John T., RE. Ginna Nuclear Power Plant, LLC, to USNRC, "Update to License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes (TSTF-286)," May 3,2011 (ADAMS Accession No. ML11129A013)

3. Memorandum from Donohew, Jack N. USNRC to Gramm, Robert A USNRC, "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)," dated May 16, 2003. (ADAMS Accession No. ML031360748)

4. Johnson, Allen R, USNRC, to Mecredy, Dr. Robert C., Rochester Gas and Electric Corporation, "Issuance of Amendment No. 61 to Facility Operating License No. DPR-18, RE. Ginna Nuclear Power Plant {TAC Nos. M89516, M89559, M92320, M92963, M92964, M92965, M92966, M92967, M92968, M92969, M93579, M93071, M93708, AND M93928)," February 13,1996. (ADAMS Accession No. ML010640012)

- 12

5. Beckner, W. D., USNRC to J. Davis, Nuclear Energy Institute, July 6, 2000. (ADAMS Accession No. ML003730788)

6. Subbaratnam, Ram US NRC to Moyer, J. W. Carolina Power & Light Company, "H. B.

Robinson Steam Electric Plant Unit 2 -Issuance of Amendment -Technical Specification Change on Operations Involving Positive Reactivity ADDITIONS (TAC No. MA9729),"

dated March 14, 2001. (ADAMS Accession No. ML010810282)

7. Wang, Alan USNRC to Randolph, Garry L. Union Electric Company, "Callaway Plant, Unit 1 - Issuance of Amendment Re: Suspension of Positive Reactivity Additions {TAC No. MB3642)," dated May 1,2002. (ADAMS Accession No. ML020220051)

8. Donohew, Jack USNRC to Maynard, Otto L. Wolf Creek Nuclear Operating Corporation, "Wolf Creek Generating Station - Issuance of Amendment Re: Limited Removal of Suspension of Positive Reactivity Additions (TAC No. MB4236}," dated July 29,2002.

(ADAMS Accession No. ML021290254)

9. Martin, Robert E. USNRC to Jamil, D. M. Duke Energy Corporation, "Catawba Nuclear Station, Units 1 and 2 Re: Issuance of Amendments (TAC Nos. MB6782 and MB6783),"

dated July 29,2003. (ADAMS Accession No. ML032110122)

10. Martin, Robert E. USNRC to Peterson, G. R Duke Energy Corporation, "McGuire Nuclear Station, Units 1 and 2 Re: Issuance of Amendments {TAC Nos. MB6784 and MB6785)," dated July 29,2003. (ADAMS Accession !\lo. ML032110073)

11. Vissing, Guy S. USNRC to Vanderheyden, George Calvert Cliffs Nuclear Power Plant, Inc., "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Amendment Re: Technical Specification Changes to Modify Requirements Related to Positive Reactivity Additions

{TAC Nos. MB8478 and MB8479)," dated May 6,2004. (ADAMS Accession No. ML040760287)

Principal Contributor: K. Bucholtz, NRR Date: June 8, 2011

June 8,2011 Mr. John T. Carlin Vice President R E. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

RE. GINNA NUCLEAR POWER PLANT - AMENDMENT RE: TECHNICAL SPECIFICATION TASK FORCE (TSTF)-286, "OPERATIONS INVOLVING POSITIVE REACTIVITY ADDITIONS" (TAC NO. ME5444)

Dear Mr. Carlin:

The Commission has issued the enclosed Amendment No. 112 to Renewed Facility Operating License No. DPR-18 for the RE. Ginna Nuclear Power Plant. This amendment is in response to your application dated July 23, 2009, as supplemented by letter dated May 3, 2011.

The amendment revises Technical Specification actions requiring suspension of operations involving positive reactivity addition and revises various notes precluding reduction in boron concentration. The amendment is consistent with Technical Specification Task Force (TSTF)-286, Revision 2, Define "Operations Involving Positive Reactivity Additions."

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, Ira!

Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosures:

1. Amendment No. 112 to Renewed License No. DPR-18

2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION; PUBLIC LPL1-1 rlf RidsNrrDorlLpl1-1 RidsNrrPMREGinna RidsOgcMailCenter RidsAcrsAcnwMailCenter SLittie RidsNrrDirsltsb Region 1MailCenter KBuchholtz GDentel, R1 ADAMS Accession No ML110980569 OFFICE LPL 1-1\PM LPL 1-1\LA ITSB\BC OGC LPL 1-1\BC NAME DPickett SLittle REliiott DRoth NSalgado (RGuzman for)

DATE 05/19/11 05/18/11 06/13/11 06/07/11 06/08/11 OffiCial Record Copy

v t e Letter Sequence Approval
TAC:ME5444, Define Operations Involving Positive Reactivity Additions (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval Other:
MONTHYEAR2011-05-03 [Table View]

ML110980569

Text

SUBJECT:

Dear Mr. Carlin:

Enclosures:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

7.0 REFERENCES

SUBJECT:

Dear Mr. Carlin:

Enclosures:

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