Text

Issuance of Amendments Adoption of TSTF-425
	ML16005A234
Person / Time
Site:	Susquehanna
Issue date:	05/20/2016
From:	Jeffrey Whited; Plant Licensing Branch 1
To:	Franke J; Susquehanna
	Whited J, NRR/DORL/LPLI-2
References
	CAC MF5151, CAC MF5152
	Download: ML16005A234 (282)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 20, 2016 Mr. Jon A. Franke Site Vice President Susquehanna Nuclear, LLC 769 Salem Boulevard NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: ADOPTION OF TSTF-425 (CAC NOS. MF5151 AND MF5152)

Dear Mr. Franke:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment Nos. 266 and 247 to Renewed Facility Operating License (RFOL) Nos. NPF-14 and NPF-22, for the Susquehanna Steam Electric Station, Units 1 and 2, respectively. These amendments consist of changes to the RFOLs in response to your application dated October 27, 2014, as supplemented by letters dated July 2, 2015; September 21, 2015; November 11, 2015; and January 29, 2016.

These amendments adopt the NRC-approved Technical Specification Task Force Traveler (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b."

A copy of the NRC staff's safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

J. Franke If you have any questions, please contact me by phone at 301-415-4090, or by e-mail at jeffrey.whited@nrc.gov.

Sincerely,

~4~

Jeffrey A. Whited, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 266 to RFOL No. NPF-14

2. Amendment No. 247 to RFOL No. NPF-22

3. Safety Evaluation cc w/enclosures: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SUSQUEHANNA NUCLEAR. LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 266 Renewed License No. NPF-14

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A The application for the amendment filed by Susquehanna Nuclear, LLC, dated October 27, 2014, as supplemented by letters dated July 2, 2015; September 21, 2015; November 11, 2015; and January 29, 2016, 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 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.

Enclosure 1

2. Accordingly, the license is amended by changes to the Renewed Facility Operating License as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 266, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. The license amendment is effective as of its date of issuance and shall be implemented within 180 days of issuance.

FOR THE NUCLEAR REG UrTORY COMMISSION

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Douglas A. Broaddus, Chie, Plant Licensing Branch 1-2 1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: May 20, 2016

ATTACHMENT TO LICENSE AMENDMENT NO. 266 RENEWED FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following page of the Renewed 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 INSERT 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 INSERT TS/3.1-10 TS I 3.1-10 TS I 3.1-13 TS I 3.1-13 TS I 3.1-17 TS I 3.1-17 TS I 3.1-19 TS I 3.1-19 TS I 3.1-21 TS I 3.1-21 TS I 3.1-22 TS I 3.1-22 TS I 3.1-26 TS I 3.1-26 TS I 3.2-2 TS I 3.2-2 TS I 3.2-4 TS I 3.2-4 TS I 3.2-6 TS I 3.2-6 TS I 3.3-3 TS I 3.3-3 TS I 3.3-4 TS I 3.3-4 TS I 3.3-5 TS I 3.3-5 TS I 3.3-6 TS I 3.3-6

TS I 3.3-6a TS I 3.3-12 TS I 3.3-12 TS I 3.3-13 TS I 3.3-13

TS I 3.3-13a TS I 3.3-18 TS/3.3-18

REMOVE INSERT TS/3.3-19 TS I 3.3-19 TS I 3.3-22 TS I 3.3-22 TS I 3.3-24 TS I 3.3-24 TS I 3.3-27 TS I 3.3-27 TS I 3.3-31 TS I 3.3-31 TS I 3.3-32 TS I 3.3-32 TS I 3.3-34 TS I 3.3-34 TS I 3.3-35 TS I 3.3-35 TS I 3.3-41 TS I 3.3-41 TS I 3.3-50 TS I 3.3-50 TS I 3.3-55 TS I 3.3-55 TS I 3.3-56 TS I 3.3-56 TS I 3.3-65 TS I 3.3-65 TS I 3.3-70 TS I 3.3-70 TS I 3.3-73 TS I 3.3-73 TS I 3.3-76 TS I 3.3-76 TS I 3.3-77 TS I 3.3-77 TS I 3.4-3 TS I 3.4-3 TS I 3.4-7 TS I 3.4-7 TS I 3.4-11 TS I 3.4-11 TS I 3.4-16 TS I 3.4-16 TS I 3.4-18 TS I 3.4-18 TS I 3.4-21 TS I 3.4-21 TS I 3.4-23 TS I 3.4-23 TS I 3.4-26 TS I 3.4-26 TS I 3.4-28 TS I 3.4-28 TS I 3.4-29 TS I 3.4-29 TS I 3.4-31 TS I 3.4-31 TS I 3.5-4 TS I 3.5-4 TS I 3.5-6 TS I 3.5-6 TS I 3.5-7 TS I 3.5-7

REMOVE INSERT TS/ 3.5-9 TS/ 3.5-9 TS/ 3.5-10 TS/ 3.5-10 TS/ 3.5-11 TS I 3.5-11 TS/3.5-13 TS/3.5-13 TS/ 3.5-14 TS/ 3.5-14 TS/ 3.6-3 TS/ 3.6-3 TS/ 3.6-7 TS/ 3.6-7 TS/ 3.6-12 TS/3.6-12 TS/3.6-13 TS/ 3.6-13 TS/ 3.6-14 TS/ 3.6-14 TS/3.6-15 TS/ 3.6-15 TS/3.6-17 TS/ 3.6-17 TS/3.6-18 TS/3.6-18 TS/ 3.6-20 TS/ 3.6-20 TS/ 3.6-21 TS/ 3.6-21 TS/ 3.6-24 TS/ 3.6-24 TS/ 3.6-25 TS/ 3.6-25 TS/ 3.6-27 TS/ 3.6-27 TS/ 3.6-29 TS/ 3.6-29 TS/ 3.6-33 TS/ 3.6-33 TS/ 3.6-34 TS/ 3.6-34 TS/ 3.6-36 TS/ 3.6-36 TS/ 3.6-37 TS I 3.6-37 TS/ 3.6-41 TS/ 3.6-41 TS/ 3.6-44 TS/ 3.6-44 TS/ 3.7-3 TS/ 3.7-3 TS/ 3.7-3a TS/ 3.7-3a TS/ 3.7-5 TS/ 3.7-5 TS/ 3.7-8 TS/ 3.7-8 TS/3.7-12 TS/ 3.7-12 TS/ 3.7-14 TS/ 3.7-14

REMOVE INSERT TS I 3.7-16 TS I 3.7-16 TS I 3.7-17 TS I 3.7-17 TS I 3.7-19 TS/3.7-19 TS I 3.8-4 TS I 3.8-4 TS I 3.8-5 TS I 3.8-5 TS I 3.8-6 TS I 3.8-6 TS I 3.8-7 TS I 3.8-7 TS I 3.8-8 TS I 3.8-8 TS I 3.8-9 TS I 3.8-9 TS/3.8-10 TS/3.8-10 TS I 3.8-11 TS I 3.8-11 TS/3.8-12 TS I 3.8-12 TS/3.8-13 TS/3.8-13 TS I 3.8-14 TS I 3.8-14 TS I 3.8-15 TS/3.8-15 TS I 3.8-16 TS I 3.8-16 TS I 3.8-22 TS I 3.8-22 TS I 3.8-24 TS I 3.8-24 TS I 3.8-25 TS I 3.8-25 TS I 3.8-35 TS I 3.8-35 TS I 3.8-36 TS I 3.8-36 TS I 3.8-39 TS I 3.8-39 TS I 3.8-43 TS I 3.8-43 TS I 3.9-2 TS I 3.9-2 TS I 3.9-3 TS I 3.9-3 TS I 3.9-4 TS I 3.9-4 TS I 3.9-5 TS I 3.9-5 TS I 3.9-8 TS I 3.9-8 TS I 3.9-9 TS I 3.9-9 TS I 3.9-12 TS I 3.9-12 TS I 3.9-15 TS I 3.9-15

REMOVE INSERT TS/ 3.10-5 TS/ 3.10-5 TS/ 3.10-8 TS/ 3.10-8 TS/3.10-11 TS/ 3.10-11 TS/ 3.10-12 TS/ 3.10-12 TS/ 3.10-14 TS/ 3.10-14 TS/ 3.10-15 TS/ 3.10-15 TS/ 3.10-17 TS/ 3.10-17 TS/ 3.10-22 TS/ 3.10-22 TS/ 3.10-23 TS/ 3.10-23 TS/ 5.0-18C TS/ 5.0-18C

(3) Susquehanna Nuclear, LLC, 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 neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Susquehanna Nuclear, LLC, 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) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational tests, startup tests and other items identified in License Conditions 2.C.(36), 2.C.(37), 2.C.(38), and 2.C.(39) to this license shall be completed as specified.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 266 and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 178 to Facility Operating License No. NPF-14, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 178. For SRs that existed prior to Amendment 178, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 178.

Renewed Operating License No. NPF-14 Amendment No. 266

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with the Surveillance Frequency SR 3.1.3.1 Determine the position of each control rod.

Control Program SR 3.1.3.2 NOT USED SR 3.1.3.3 ---------------------------NOTE---------------------------

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

In accordance with the Insert each withdrawn control rod at least one Surveillance Frequency notch.

Control Program SR 3.1.3.4 Verify each control rod scram time from fully In accordance with withdrawn to notch position 05 is ~ 7 seconds. SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)

SUSQUEHANNA - UNIT 1 TS/3.1-10 Amendment 4-78,-2-W;- 266 I

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested In accordance with the control rod scram time is within the limits of Surveillance Frequency Table 3.1.4-1 with reactor steam dome pressure Control Program

~ 800 psig.

Prior to declaring control rod SR 3.1.4.3 Verify each affected control rod scram time is OPERABLE after work on within the limits of Table 3.1.4-1 with any reactor control rod or CRD System steam dome pressure.

that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding 40% RTP within the limits of Table 3.1.4-1 with reactor after fuel movement within steam dome pressure~ 800 psig. the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time SUSQUEHANNA - UNIT 1 TS/3.1-13 Amendment .:i.+g, 237, 24 Q, 266 I

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control rod C.1 Verify all control rods Immediately upon scram accumulators associated with inoperable discovery of charging inoperable with reactor accumulators are fully water header pressure steam dome pressure inserted. < 940 psig

< 900 psig.

AND C.2 Declare the associated control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod inoperable.

D. Required Action and D.1 -------------N 0 TE--------------

associated Completion Not applicable if all inoperable Time of Required Action control rod scram B.1 or C.1 not met. accumulators are associated with fully inserted control rods.

Place the reactor mode switch Immediately in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram In accordance with the Surveillance accumulator nitrogen pressure is Frequency Control Program

940 psig.

SUSQUEHANNA - UNIT 1 TS I 3.1-17 Amendment-1-78,-266 I

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION Tl ME B. Nine or more OPERABLE B.1 ---------------NOTE---------------

control rods not in Rod worth minimizer (RWM) compliance with BPWS. may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal of Immediately control rods.

AND B.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months sw~ch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with In accordance with the BPWS. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/3.1-19 Amendment 4-18, 266 I

SLC SYSTEM 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate In accordance with the solution is within the limits of Figure 3.1. 7-1. Surveillance Frequency Control Program SR 3.1.7.2 Verify temperature of sodium pentaborate solution In accordance with the is within the limits of Figure 3.1.7-2. Surveillance Frequency Control Program SR 3.1.7.3 Verify temperature of pump suction piping is within In accordance with the the limits of Figure 3.1.7-2. Surveillance Frequency Control Program SR 3.1. 7.4 Verify continuity of explosive charge. In accordance with the Surveillance Frequency Control Program SR 3.1. 7.5 Verify the concentration of sodium pentaborate in In accordance with the solution is within the limits of Figure 3.1.7-1. Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 (continued)

SUSQUEHANNA - UNIT 1 TS I 3.1-21 Amendment t78,~ 266 j

SLC SYSTEM 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual and power In accordance with the operated valve in the flow path that is not locked, Surveillance Frequency sealed, or otherwise secured in position is in the Control Program correct position, or can be aligned to the correct position.

SR 3.1.7.7 Verify each pump develops a flow rate 240.0 gpm In accordance with the at a discharge pressure 21250 psig. lnservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem pump into In accordance with the reactor pressure vessel. Surveillance Frequency Control Program SR 3.1.7.9 Verify all heat traced piping between storage tank In accordance with the and pump suction is unblocked. Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 SR 3.1. 7 .1 O Verify sodium pentaborate enrichment is Prior to addition to SLC tank.

288 atom percent 8-10.

SUSQUEHANNA - UNIT 1 TS/ 3.1-22 Amendment V6, m ;-249, 266 I

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 -----------------------------NOTE-----------------------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. In accordance with the Surveillance Frequency Control Proqram SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully In accordance with the closed and fully open position. Surveillance Frequency Control Program SR 3.1.8.3 Verify each SDV vent and drain valve: In accordance with the Surveillance Frequency

a. Closes in '.":'.; 30 seconds after receipt of an Control Program actual or simulated scram signal; and

b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT 1 TS I 3.1-26 Amendment 1-78, 266 I

APLHGR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after to the limits specified in the COLR. :2:23% RTP In accordance with the Surveillance Frequency Control Program Prior to exceeding 44% RTP SUSQUEHANNA - UNIT 1 TS I 3.2-2 Amendment V$,-246, 266 I

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the limits specified in the COLR. ~ 23% RTP In accordance with the Surveillance Frequency Control Program Prior to exceeding 44% RTP SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SRs in 3.1.4 SUSQUEHANNA - UNIT 1 TS/ 3.2-4 Amendment ;fa,~ 266 I

LHGR 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the limits specified in the COLR. ;::: 23% RTP In accordance with the Surveillance Frequency Control Program Prior to exceeding 44% RTP SUSQUEHANNA - UNIT 1 TS I 3.2-6 Amendment .p.g, 2-4&,. 266 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

NOTES-----------------------------------------------------------

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.3 -------------------------------NOTE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER~ 23% RTP.

Verify the absolute difference between the average In accordance with power range monitor (APRM) channels and the the Surveillance calculated power is ::;; 2% RTP while operating at Frequency Control

~ 23% RTP. Program SR 3.3.1.1.4 -------------------------------N 0 TE-------------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.3-3 Amendment 1-?CS, 230, ~ 246r 266

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to fully intermediate range monitor (IRM) channels overlap. withdrawing SRMs from the core.

SR 3.3.1.1.7 ------------------------------NOTE-------------------------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.9 ------------------------------N 0 TE-------------------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.3-4 Amendment .++g, 246-. 2661

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 ------------------------------N 0 TES------------------------------

1. Neutron detectors are excluded.

2. For Function 1.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE2.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.12 ------------------------------NOTES------------------------------

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.3-5 Amendment 17%,'230, 246, 266 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.13 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Proqram SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and Turbine In accordance with Control Valve Fast Closure, Trip Oil Pressure-Low the Surveillance Functions are not bypassed when THERMAL Frequency Control POWER is ~ 26% RTP. Program SR 3.3.1.1.17 -------------------------------N 0 TES-----------------------------

1. Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Proqram (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.3-6 Amendment J.9'1, iaD, 246, 266 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.18 -------------------------------N 0 TES-----------------------------

1. Neutron detectors are excluded.

2. For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM Simulated In accordance with Thermal Power is ~ 25% and recirculation drive flow the Surveillance is s value equivalent to the core flow value defined in Frequency Control the COLR. Program SR 3.3.1.1.20 Adjust recirculation drive flow to conform to reactor In accordance with core flow. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-6a Amendment 266 I

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2 ---------------------------------N 0 TES---------------------------

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following Verify an OPERABLE SRM detector is located in: In accordance with the Surveillance Frequency Control Program

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.3-12 Amendment 4-7&,-266 I

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.4 ------------------------------N 0 TE--------------------------------

Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS

a. z 3.0 cps if a signal to noise ratio z 2:1 or In accordance with

b. Within the limits of Figure 3.3.1.2-1 the Surveillance Frequency Control Program SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST and In accordance with determination of signal to noise ratio. the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.3-13 Amendment f-18, 266 I

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.6 -----------------------------N 0 TE--------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST and In accordance with determination of signal to noise ratio. the Surveillance Frequency Control Program SR 3.3.1.2. 7 -----------------------------N 0 TES-------------------------------

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.3-13a Amendment 266 I

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

NOTES--------------------------------------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3. 3. 2. 1.2 ---------------------------------N 0 TE-----------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at ::; 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3. 3. 2. 1.3 ---------------------------------N 0 TE-----------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is ::; 10% RTP in MODE 1.

In accordance with Perform CHANNEL FUNCTIONAL TEST. the Surveillance Frequency Control Program SR 3.3.2.1.4 Verify the RBM:

a. Low Power Range - Upscale Function is not bypassed In accordance with when APRM Simulated Thermal Power is ~ 28% RTP the Surveillance and::; Intermediate Power Range Setpoint specified in Frequency Control the COLR. Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.3-18 Amendment rn~o. Z4Z; 266 I

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

b. Intermediate Power Raige - Upscale Function is not bypassed when APRM Simulated Thermal Power is> Intermediate Power Range Setpoint specified in the COLR and ::;; High Power Range Setpoint specified in the COLR.

c. High Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power is > High Power Range Setpoint specified in the COLR.

SR 3.3.2.1.5 Verify the RWM is not bypassed when THERMAL POWER In accordance with is::;; 10% RTP. the Surveillance Frequency Control Program SR 3. 3. 2. 1. 6 -----------------------------------NOTE---------------------------~--------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.1. 7 -----------------------------------NOTE------------------------------------

Neutron detectors are excluded.

In accordance with Perform CHANNEL CALIBRATION the Surveillance Frequency Control Program SR 3.3.2.1.8 Verify control rod sequences input to the RWM are in Prior to declaring conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SUSQUEHANNA - UNIT 1 TS/ 3.3-19 Amendment 1:fa, 242, 266 I

Feedwater- Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS

NOTE---------------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater - main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.2

1. A test of all required contacts does not have to be performed.

2. For the Feedwater - Main Turbine High Water Level Function, a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The Allowable In accordance with Value shall be::; 55.5 inches. the Surveillance Frequency Control Program SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST including In accordance with valve actuation. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.3-22 Amendment ~266 I

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition referenced Immediately associated in Table 3.3.3.1-1 for the Completion Time of channel.

Condition C not met.

E. As required by E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by F.1 Initiate action in accordance with Immediately Required Action D.1 Specification 5.6.7.

and referenced in Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

N 0 TE---------------------------------------------------------------

These SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.3.1.2 Not Used.

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for all Functions In accordance with the except PCIV Position. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-24 Amendment VS, 2-34, 266 I

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS

NOTE--------------------------------------------------------------

Refer to Table 3.3.3.2-1 to determine which SRs apply for each Remote Shutdown System Function.

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.3.2.2 Verify each required control circuit and transfer In accordance with sw~ch is capable of performing the intended the Surveillance function. Frequency Control Program SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each In accordance with required instrumentation channel. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-27 Amendment 1-78, 266 I

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

NOTE--------------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required SuNeillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.1.2 Perform CHANNEL CALIBRATION. The Allowable Values In accordance with shall be: the Surveillance Frequency Control Program TSV-Closure: ~7% closed; and TCV Fast Closure, Trip Oil Pressure-Low: ~ 460 psig.

SR 3.3.4.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST including In accordance with breaker actuation. the Surveillance Frequency Control Program SR 3.3.4.1.4 Verify TSV-Closure and TCV Fast Closure, Trip Oil In accordance with Pressure-Low Functions are not bypassed when the Surveillance THERMAL POWER is ~ 26% RTP. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.3-31 Amendment ya, ~ 266 I

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 3. 4. 1.5 ---------------------------------N 0 TE-----------------------------------

Brea ker arc suppression time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME is within In accordance with limits. the Surveillance Frequency Control Program SR 3.3.4.1.6 Determine RPT breaker arc suppression time. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-32 Amendment t-78., 266 I

ATWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Function with B.1 Restore ATWS-RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ATWS-RPT trip capability.

capability not maintained.

C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months A TWS-RPT trip capability for one Function.

capability not maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated recirculation pump from service.

Completion Time not met.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK of Reactor Vessel Water In accordance with Level, Low Low, Level 2. the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.3-34 Amendment 1-78, 266 I

PPL Rev.

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.2.3 Perform CHANNEL CALIBRATION of the Reactor In accordance with Steam Dome Pressure-High. The Allowable Values shall the Surveillance be~ 1150 psig. Frequency Control Program SR 3.3.4.2.4 Perform CHANNEL CALIBRATION of the Reactor In accordance with Vessel Water Level Low Low, Level 2. The Allowable the Surveillance Values shall be ~ -45 inches. Frequency Control Program SR 3.3.4.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST including In accordance with breaker actuation. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-35 Amendment U8;" 266 I

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.e; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.e provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Proi:iram SUSQUEHANNA - UNIT 1 TS I 3.3-41 Amendment 1-78, ~ 266

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

N 0 TES---------------------------------------------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 4 and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than Functions 2 and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-50 Amendment µa: 266 I

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is plaood in an inoperable status solely for performance of required Surveillanoos, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Proqram SR 3.3.6.1.2 1. A test of all required contacts does not have to be performed

2. For Functions 2.e, 3.a, and 4.a, a test of all required relays does not have to be performed Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Proqram SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Proqram SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.3-55 Amendment 1-lt), 266 I

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.3.6.1.6 ---------------------------N 0 TE-----------------------------

1. For Function 1.b. channel sensors are excluded.

2. Response time testing of isolating relays is not required for Function 5.a.

Verify the ISOLATION SYSTEM RESPONSE TIME In accordance with is within linits. the Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS I 3.3-56 Amendment J.9t; 266 I

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

NOTES---------------------------------------------------------

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-65 Amendment VS: 266 11

CREOAS System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS

N 0 TES---------------------------------------------------------

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREOAS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains CREOAS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2

1. A test of all required contacts does not have to be performed.

2. For Function 8, a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Proqram SUSQUEHANNA - UNIT 1 TS I 3.3-70 Amendment VB-, 266

LOP Instrumentation 3.3.8.1 CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare associated diesel Immediately associated generator (DG) inoperable.

Completion Time of Condition B or C not met.

SURVEILLANCE REQUIREMENTS

NOTES---------------------------------------------------------

1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains DG initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.3-73 Amendment V8;"'266 I

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully insert all Immediately associated insertable control rods in core Completion Time of cells containing one or more fuel Condition A or B not assemblies.

met in MODE 4 or 5.

D.2.1 Initiate action to restore one Immediately electric power monitoring assembly to OPERABLE status for inservice power supply(s) supplying required instrumentation.

D.2.2 Initiate action to isolate the Immediately Residual Heat Removal Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 ------------------------------N 0 TE-------------------------------

0 nly required to be performed prior to entering MODE 2 or 3 from MODE 4, when in MODE 4 for

~ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.3-76 Amendment ~266 I

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The Allowable In accordance with Values shall be: the Surveillance Frequency Control Program

a. Overvoltage ~ 128.3 V for Division A and

~ 129.5 V for Division B.

b. Undervoltage z 110. 7 V for Division A and z 111.9 V for Division B.

c. Underfrequency z 57 Hz.

SR 3.3.8.2.3 Perform a system functional test. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.3-77 Amendment m;-266 I

Recirculating Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 --------------------------NOTE---------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow In accordance with the mismatch with both recirculation loops in Surveillance Frequency operation is: Control Program

a. :s; 1O million lbm/hr when operating at

< 75 million lbm/hr total core flow; and

b. :s; 5 million lbm/hr when operating at

?: 75 million lbm/hr total core flow.

SR 3.4.1.2 --------------------------NOTE---------------------------

Only required to be met during single loop operations.

Verify recirculation pump speed is within the In accordance with the limit specified in the LCO. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.4-3 A~endment t?8, I

}84, 2f5, 24.:r, 266

Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3 .4. 2. 1 --------------------------NO TES-------------------------

1. Not required to be completed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2. Not required to be completed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after> 23% RTP.

Verify at least two of the following criteria (a, In accordance with the b, or c) are satisfied for each operating Surveillance Frequency recirculation loop: Control Program

a. Recirculation loop drive flow versus Recirculation Pump speed differs by

~ 10% from established patterns.

b. Recirculation loop drive flow versus total core flow differs by ~ 10% from established patterns.

c. Each jet pump diffuser to lower plenum differential pressure differs by

~ 20% from established patterns, or each jet pump flow differs by~ 10%

from established patterns.

SUSQUEHANNA - UNIT 1 TS/ 3.4-7 Amendment 1 ye, ~ 266 I

RCS Operational LEM<AGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE In accordance with the and unidentified LEAKAGE increases are Surveillance Frequency within limits. Control Program SUSQUEHANNA - UNIT 1 TS/3.4-11 Amendment 1J8;'266 I

RCS Leakage Detection Instrumentation 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Perform a CHANNEL CHECK of required primary In accordance with containment atmospheric monitoring system. the SuNeillance Frequency Control Program SR 3.4.6.2 Perform a CHANNEL FUNCTIONAL TEST of required In accordance with leakage detection instrumentation. the SuNeillance Frequency Control Proqram SR 3.4.6.3 Perform a CHANNEL CALIBRATION of required In accordance with leakage detection instrumentation. the SuNeillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/3.4-16 Amendment %, 266 I

RCS Specific Activity 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 ------------------------------N 0 TE----------------------

0 n ly required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT In accordance with the 1-131 specific activity is:<:::; 0.2 µCi/gm. SuNeillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS/3.4-18 Amendment ~. 266 I

RHR Shutdown Cooling System - Hot Shutdown 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 ----------------------------N 0 TE------------------------

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify one RHR shutdown cooling subsystem or In accordance with the recirculation pump is operating. Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS I 3.4-21 Amendment j..16, 266 I

RHR Shutdown Cooling System - Cold Shutdown 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of cooling subsystem in circulating by an alternate no reactor coolant operation. method. circulation AND No recirculation pump Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in operation. thereafter AND B.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify one RHR shutdown cooling subsystem or In accordance with the recirculation pump is operating. Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS I 3.4-23 Amendment ~ 266 I

RCS PIT Limits 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 -------------------------------NOTE-----------------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a. RCS pressure and RCS temperature are to In accordance with the the right of the most limiting curve specified Surveillance Frequency in Figures 3.4.10-1 through 3.4.10-3; and Control Program

b. ---------------------N 0 TE-----------------------------

0 nly applicable when governed by Figure 3.4.10-2, Curve B, and Figure 3.4.10-3, Curve C.

RCS heatup and cooldown rates are

100°F in any one hour period; and

c. ---------------------N 0 TE-----------------------------

0 nly applicable when governed by Figure 3.4.10-1, Curve A.

RCS heatup and cooldown rates are:::; 20°F in any one hour period.

SR 3.4.10.2 Verify RCS pressure and RCS temperature are to Once within 15 minutes the right of the criticality limit (Curve C) specified in prior to control rod Figure 3.4.10-3. withdrawal for the purpose of achieving criticality (continued)

SUSQUEHANNA - UNIT 1 TS I 3.4-26 Amendment 200;' 266 I

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.6 ----------------------------N 0 TE----------------------------

0 nly required to be met in single loop operation when the idle recirculation loop is not isolated from the RPV, and:

a. THERMAL POWER::;; 27% RTP; or

b. The operating recirculation loop flow

21,320 gpm.

Verify the difference between the reactor coolant Once within 15 minutes temperature in the recirculation loop not in prior to an increase in operation and the RPV coolant temperature is THERMAL POWER or

50°F. an increase in loop flow.

SR 3.4.10.7 ----------------------------NOTE----------------------------

0 nly required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange In accordance with the temperatures are 2: 70°F. Surveillance Frequency Control Proqram SR 3.4.10.8 ----------------------------NOTE----------------------------

Not required to be performed until 30 minutes after RCS temperature::;; 80°F in MODE 4.

Verify reactor vessel flange and head flange In accordance with the temperatures are 2: 70°F. Surveillance Frequency Control Proqram (continued)

SUSQUEHANNA - UNIT 1 TS I 3.4-28 Amendment 178, 246;266 I

RCS PIT Limits 3.4.10 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.4.10.9 ----------------------------NOTE----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature :5: 100°F in MODE 4.

Verify reactor vessel flange and head flange In accordance with the temperatures are ;;::: 70°F. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.4-29 Amendment :1-78; 266 I

Reactor Steam Dome Pressure 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Reactor Steam Dome Pressure LCO 3.4.11 The reactor steam dome pressure shall be~ 1050 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within dome pressure to within limit. limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify reactor steam dome pressure is In accordance with the

~ 1050 psig. SuNeillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS I 3.4-31 Amendment ~66 I

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, In accordance with the the piping is filled with water from the pump Surveillance Frequency discharge valve to the injection valve. Control Program SR 3.5.1.2 -----------------------------N 0 TE-----------------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in In accordance with the the flow path, that is not locked, sealed, or Surveillance Frequency otherwise secured in position, and the HPCI flow Control Program controller are in the correct position.

SR 3.5.1.3 Verify ADS gas supply header pressure is In accordance with the

135 psig. Surveillance Frequency Control Program SR 3.5.1.4 Verify at least one RHR System cross tie valve is In accordance with the closed and power is removed from the valve Surveillance Frequency operator. Control Program SR 3.5.1.5 Verify each 480 volt AC swing bus transfers In accordance with the automatically from the normal source to the Surveillance Frequency alternate source on loss of power. Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.5-4 Amendment 1..18-;- 266 I

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 5 .1. 9 ----------------------------NO TE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure::;;; 165 psig, the HPCI In accordance with the pump can develop a flow rate~ 5000 gpm against Surveillance Frequency a system head corresponding to reactor pressure. Control Program SR 3.5.1.10 --------------------------------NOTE--------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with the actuates on an actual or simulated automatic Surveillance Frequency initiation signal. Control Program SR 3.5.1.11 -------------------------------NOTE---------------------------

Valve actuation may be excluded.

In accordance with the Verify the ADS actuates on an actual or simulated Surveillance Frequency automatic initiation signal. Control Program SR 3.5.1.12 Verify each ADS valve actuator strokes when In accordance with the manually actuated. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.5-6 Amendment 4-78, ~. 266 I

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.5.1.13 --------------------------NOTE--------------------------------

1nstrumentation response time is based on historical response time data.

Verify the ECCS RESPONSE TIME for each In accordance with the ECCS injection/spray subsystem is within limit. Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS I 3.5-7 Amendment ~ 266 I

ECCS-Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate action to restore Immediately associated Completion Time secondary containment to not met. OPERABLE status.

D.2 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

D.3 Initiate action to restore isolation Immediately capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure coolant In accordance with the injection (LPCI) subsystem, the suppression pool Surveillance Frequency water level is ~ 20 ft O inches. Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.5-9 Amendment JIB; 266 I

ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required core spray (CS) In accordance with the subsystem, the: Surveillance Frequency Control Program

a. Suppression pool water level is

~ 20 ft 0 inches; or

b. -------------------------N 0 TE--------------------------

0 nly one required CS subsystem may take credit for this option during OPDRVs.

Condensate storage tank water level is

~ 49% of capacity.

SR 3.5.2.3 Verify, for each required ECCS injection/spray In accordance with the subsystem, the piping is filled with water from the Surveillance Frequency pump discharge valve to the injection valve. Control Program SR 3. 5. 2.4 -------------------------------NOTE---------------------------

LPC I subsystems may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray In accordance with the subsystem manual, power operated, and Surveillance Frequency automatic valve in the flow path, that is not locked, Control Program sealed, or otherwise secured in position, is in the correct position.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.5-10 Amendment~ 266 I

ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each required ECCS pump develops the In accordance with the specified flow rate against a system head lnservice Testing Program corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO.OF TOA REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs ~ 6350 gpm 2 ~ 105 psig LPCI ~ 12,200 gpm 1 ~ 20 psig SR 3. 5. 2. 6 -----------------------------NO TE-----------------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray In accordance with the subsystem actuates on an actual or simulated Surveillance Frequency automatic initiation signal. Control Program SR 3. 5. 2 .7 ------------------------------N 0 TE----------------------------

1nstru mentati on response time may be assumed to be the historical instrumentation response time.

Verify the ECCS RESPONSE TIME for each In accordance with the ECCS injection/spray subsystem is within limit. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.5-11 Amendment )Ar, 266 I

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with water from In accordance with the pump discharge valve to the injection valve. the Surveillance Frequency Control Proqram SR 3.5.3.2 Verify each RCIC System manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, the Surveillance sealed, or otherwise secured in position, and the RCIC Frequency Control flow controller are in the correct position. Program SR 3. 5. 3. 3 ----------------------------------NO TE---------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure ~ 1060 psig and In accordance

~ 920 psig, the RCIC pump can develop a flow rate with the lnservice

~ 600 gpm against a system head corresponding to Testing Program reactor pressure.

SR 3. 5. 3. 4 ------------------------------------NO TE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure ~ 165 psig, the RCIC pump In accordance with can develop a flow rate ~ 600 gpm against a system the Surveillance head corresponding to reactor pressure. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.5-13 Amendment :l.1-8'; 266 I

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 5. 3. 5 ----------------------------------N 0 TE---------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.5-14 Amendment 1-78, 266 I

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.6.1.1.3 ------------------------------Note------------------------------

Satisfied by the performance of SR 3.6.1.1.2.

Verify that the total drywell-to-suppression In accordance with the chamber vacuum breaker leakage is less than or SuNeillance Frequency 2

equal to .001605 ft and the leakage area for each Control Program set of vacuum breakers is less than or equal to 2

.000642 ft at an initial differential pressure of

~ 4.3 psi.

SUSQUEHANNA - UNIT 1 TS/ 3.6-3 Amendment )J8", 266 I

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 -------------------------NOTES--------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria acceptable to SR 3.6.1.1.1.

Perform required primary containment air lock In accordance with leakage rate testing in accordance with the the Primary Primary Containment Leakage Rate Testing Containment Leakage Program. Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary In accordance with containment air lock can be opened at a time. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-7 Amendment VB;- 266 I

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ---------------------------NOTES----------------------------

1. Only required to be met in MODES 1, 2, and 3.

2. Not required to be met when the 18 and 24 inch primary containment purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 and 24 inch primary containment In accordance with purge valve is closed. the Surveillance Frequency Control Program SR 3.6.1.3.2 ---------------------------NOTES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual In accordance with valve and blind flange that is located outside the Surveillance primary containment and not locked, sealed, or Frequency Control otherwise secured and is required to be closed Program during accident conditions is closed.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.6-12 Amendment :i.:re;-266 I

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 ----------------------------N 0 TES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside primary MODE 2 or 3 from containment and not locked, sealed, or otherwise MODE 4 if primary secured and is required to be closed during containment was accident conditions is closed. de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity for each of the traversing incore In accordance with probe (TIP) shear isolation val\ie explosive charge. the Surveillance Frequency Control Proo ram SR 3.6.1.3.5 Verify the isolation time of each power operated In accordance and each automatic PCIV, except for MSIVs, is with the lnservice within limits. Testing Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.6-13 Amendment :lJ8; 266 I

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.6 ----------------------------N 0 TE------------------------------

0 n ly required to be met in MODES 1, 2 and 3.

Perform leakage rate testing for each primary In accordance with containment purge valve with resilient seals. the Surveillance Frequency Control Program SR 3.6.1.3. 7 Verify the isolation time of each MSIV is In accordance z 3 seconds and ~ 5 seconds. with the lnservice Testing Program SR 3.6.1.3.8 Verify each automatic PCIV actuates to the In accordance with isolation position on an actual or simulated the Surveillance isolation signal. Frequency Control Program SR 3.6.1.3.9 Verify a representative sample of reactor In accordance with instrumentation line EFCVs actuate to check flow the Surveillance on a simulated instrument line break. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.6-14 AmendmentA-9"3, m 266 I

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.10 Remove and test the explosive squib from each In accordance with shear isolation val~ of the TIP System. the Surveillance Frequency Control Program SR 3.6.1.3.11 ----------------------------NOTES----------------------------

Only required to be met in MODES 1, 2, and 3.

Verify the combined leakage rate for all secondary In accordance containment bypass leakage paths is ~ 15 scfh with the Primary when pressurized to~ Pa. Containment Leakage Rate Testing Program.

SR 3.6.1.3.12 ----------------------------N 0 TES----------------------------

0 nly required to be met in MODES 1, 2, and 3.

Verify leakage rate through each MSIV is In accordance

~ 100 scfh and ~300 scfh for the combined with the Primary leakage including the leakage from the MS Line Containment Drains, when the MSIVs are tested at~ 24.3 psig Leakage Rate or Pa and the MS Line Drains are tested at Pa. Testing Program.

(continued)

SUSQUEHANNA - UNIT 1 TS/ 3.6-15 Amendment +w, 24-e, 251"; 266 I

Containment Pressure 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Containment Pressure LCO 3.6.1.4 Containment pressure shall be -1.0 to 2.0 psig.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure not A.1 Restore containment pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limit to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with the SR 3.6.1.4.1 Verify containment pressure is within limit.

Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-17 Amendment V8:"266 I

Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Drywell Air Temperature LCO 3.6.1.5 Drywell average air temperature shall be ::::; 135°F.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell average air 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within temperature to within limit.

limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify drywell average air temperature is within limit. In accordance with the Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 1 TS I 3.6-18 Amendment 1.16, 266 I

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 ------------------------------N 0 TE----------------------------

Not required to be met for vacuum breakers that are open during Surveillances.

In accordance with Verify each vacuum breaker is closed.

the Surveillance Frequency Control Program AND Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after discharge of steam to the suppression chamber from safety/relief valve (S/RV) operation.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.6-20 Amendment 1J.&,- 266 I

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY In accordance with SR 3.6.1.6.2 Perform a functional test of each required vacuum the Surveillance breaker. Frequency Control Program Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after discharge of steam to the suppression chamber from S/RV operation AND Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following an operation that causes any of the vacuum breakers to open SR 3.6.1.6.3 Verify the opening setpoint of each required In accordance with vacuum breaker is;;:: 0.25 and :s; .75 psid. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-21 Amendment 198;266 I

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool average E.1 Depressurize the reactor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperature> 120°F. vessel to< 200 psig.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is In accordance with the within the applicable limits. Surveillance Frequency Control Program 5 minutes when performing testing that adds heat to the suppression pool SUSQUEHANNA - UNIT 1 TS I 3.6-24 Amendment 1,A(, 266 I

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be ~ 22 ft O inches and ~ 24 ft 0 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Suppression pool water level A.1 Restore suppression pool 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not within limits. water level to within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is In accordance with the Surveillance within limits. Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-25 Amendment 17&,-266 /

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance with the subsystem manual, power operated, and Surveillance Frequency automatic valve in the flow path that is not locked, Control Program sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance with the

> 9750 gpm through the associated heat lnservice Testing Program exchanger while operating in the suppression pool cooling mode.

SUSQUEHANNA - UNIT 1 TS I 3.6-27 Amendment 1J8;L66 I

RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray In accordance with the subsystem manual, power operated, and Surveillance Frequency automatic valve in the flow path that is not locked, Control Program sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.4.2 Verify each suppression pool spray is In accordance with the unobstructed. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-29 Amendment V6, 266 I

Drywell Air Flow System 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Operate each required drywell cooling fan at low In accordance with the speed for ~ 15 minutes. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-33 Amendment m. 266 I

Primary Containment Oxygen Concentration 3.6.3.3 3.6 CONTAINMENT SYSTEMS 3.6.3.3 Primary Containment Oxygen Concentration LCO 3.6.3.3 The primary containment oxygen concentration shall be < 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to ::;; 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Primary containment oxygen A.1 Restore oxygen concentration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months concentration not within limit. to within limit.

B. Required Action and B.1 Reduce THERMAL POWER to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion Time :::; 15% RTP.

not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.3.1 Verify primary containment oxygen concentration In accordance with the is within limits. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/ 3.6-34 Amendment V8. 266 I

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment C.1 -----------------N 0 TE----------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies ----------------------------------------

in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

AND C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is In accordance with the

~ 0.25 inch of vacuum water gauge. Surveillance Frequency Control Pro ram SR 3.6.4.1.2 Verify all required secondary containment In accordance with the removable walls and equipment hatches required Surveillance Frequency to be closed are closed and sealed. Control Program (continued)

SUSQUEHANNA - UNIT 1 TS/ 3.6-36 Amendment 178, 2i4, 226, 266 I

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

N 0 TE-----------------------------

S in g Ie door access openings between required zones within the secondary containment boundary may be opened for entry and exit.

SR 3.6.4.1.3 Verify one secondary containment access door in In accordance with the each access opening is closed. Surveillance Frequency Control Program SR 3.6.4.1.4 -----------------------------NOTE----------------------------- ---------------N 0 TE----------------

The maximum time allowed for secondary T est each configuration at containment draw down is dependent on the least one time every 60 secondary containment configuration. months.

Verify each standby gas treatment (SGT) In accordance with the subsystem will draw down the secondary Surveillance Frequency containment to ~ 0.25 inch of vacuum water gauge Control Program in less than or equal to the maximum time allowed for the secondary containment configuration that is OPERABLE.

SR 3.6.4.1.5 -----------------------------NOTE---------------------------- ---------------N 0 TE----------------

The maximum flow allowed for maintaining T est each configuration at secondary containment vacuum is dependent on least one time every 60 the secondary containment configuration. months.

Verify each SGT subsystem can maintain In accordance with the

~ 0.25 inch of vacuum water gauge in the Surveillance Frequency secondary containment for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow Control Program rate less than or equal to the maximum flow rate permitted for the secondary containment configuration that is OPERABLE.

SUSQUEHANNA - UNIT 1 TS I 3.6-37 Amendment 1is, 2fl6, 229; 266 I

SC IVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 6 .4. 2. 1 ----------------------------NO TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each required secondary containment In accordance with the isolation manual valve and blind flange that is Surveillance Frequency required to be closed during accident conditions is Control Program closed.

SR 3.6.4.2.2 Verify the isolation time of each required In accordance with the automatic SCIV is within limits. Surveillance Frequency Control Proqram SR 3.6.4.2.3 Verify each required automatic SCIV actuates to In accordance with the the isolation position on an actual or simulated Surveillance Frequency actuation signal. Control Program SUSQUEHANNA - UNIT 1 TS I 3.6-41 Amendment V8; 266 I

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two SGT subsystems F.1 ----------------NOTE----------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of irradiated fuel Immediately ALTERATIONS, or during assemblies in secondary OPDRVs. containment.

F.2 Suspend CORE ALTERATIONS. Immediately F.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT filter train for:?: 10 continuous In accordance with the hours with heaters operating. Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the VFTP with the Ventilation Filter Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual In accordance with the or simulated initiation signal. Surveillance Frequency Control Prooram SR 3.6.4.3.4 Verify each SGT filter cooling bypass and outside In accordance with the air damper opens and the fan starts on high Surveillance Frequency charcoal temperature. Control Program SUSQUEHANNA - UNIT 1 TS/ 3.6-44 Amendment 1f8, ~. 266 I

RHRSW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify the water level is greater than or equal to 678 feet In accordance with 1 inch above Mean Sea Level. the Surveillance Frequency Control Program SR 3.7.1.2 Verify the average water temperature of the UHS is: In accordance with the Surveillance Frequency Control Program

a. --------------------------------N 0 TE--------------------------------

0 nly applicable with both units in MODE 1 or 2, or with either unit in MODE 3 for less than twelve (12) hours.

~ 85°F; or

. b. --------------------------------N 0 TE--------------------------------

0 nly applicable when either unit has been in MODE 3 for at least twelve ( 12) hours but not more than twenty-four (24) hours.

~ 87°F; or

c. --------------------------------N 0 TE--------------------------------

0 nly applicable when either unit has been in MODE 3 for at least twenty-four (24) hours.

~ 88°F SR 3.7.1.3 Verify each RHRSW manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, sealed, the Surveillance or otherwise secured in position, is in the correct position Frequency Control or can be aligned to the correct position. Program SR 3.7.1.4 Verify that valves HV-01222A and B (the spray array In accordance with bypass valves) close upon receipt of a closing signal and the Surveillance open upon receipt of an opening signal. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.7-3 AmendliTeRt 1r3, I 182 200, "246, 266

PPL Rev.

RHRSW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.5 Verify that valves HV-01224A 1 and 81 (the large spray In accordance with array valves) close upon receipt of a closing signal and the Surveillance open upon receipt of an opening signal. Frequency Control Program SR 3.7.1.6 Verify that valves HV-01224A2 and 82 (the small spray In accordance with array valves) close upon receipt of a closing signal and the Surveillance open upon receipt of an opening signal. Frequency Control Program SR 3.7.1.7 Verify that valves 012287A and 0122878 (the spray array In accordance with bypass manual valves) are capable of being opened and the Surveillance closed. Frequency Control ProQram SUSQUEHANNA - UNIT 1 TS I 3.7-3a Amendment 2e6., ~. 266 I

ESW System 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7 .2.1 --------------------------NOTE----------------------------------

lsolation of flow to individual components does not render ESW System inoperable.

Verify each ESW subsystem manual, power In accordance with the operated, and automatic valve in the flow paths Surveillance Frequency servicing safety related systems or components, Control Program that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the SR 3.7.2.2 Verify each ESW subsystem actuates on an Surveillance Frequency actual or simulated initiation signal. Control Program SUSQUEHANNA - UNIT 1 TS I 3.7-5 Amendment 1J8; 266 I

CREOAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREOAS subsystems ---------------------N 0 TE--------------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies --------------------------------------------------

in the secondary containment, during CORE F.1 Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

OR AND One or more CREOAS F.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.

to an inoperable CRE boundary during movement of irradiated fuel assemblies AND in the secondary containment, during CORE F.3 Initiate action to suspend ALTERATIONS, or during Immediately OPDRVs.

OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7.3.1 Operate each CREOAS filter train for~ 1O In accordance with the continuous hours with the heaters operable. Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREOAS filter testing in In accordance with the VFTP accordance with the Ventilation Filter Testing Program (VFTP).

SR 3.7.3.3 Verify each CREOAS subsystem actuates on an In accordance with the actual or simulated initiation signal. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.7-8 Amendment -i+g, m, 266 I

Control Room Floor Cooling System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two control room floor --------------------N 0 TE---------------------

cooling subsystems LCO 3.0.3 is not applicable.

inoperable during movement of irradiated fuel assemblies in the secondary E.1 Suspend movement of Immediately containment, during CORE irradiated fuel assemblies in ALTERATIONS, or during the secondary containment.

OPDRVs.

E.2 Suspend CORE Immediately ALTERATIONS.

E.3 Initiate actions to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with the SR 3.7.4.1 Verify each control room floor cooling subsystem Surveillance Frequency Control has the capability to remove the assumed heat Program load.

SUSQUEHANNA - UNIT 1 TS I 3.7-12 Amendment V8', 266 I

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7. 5. 1 ----------------------------N 0 TE------------------------------

Not required to be performed until 31 days after any main steam line is not isolated Verify the radioactivity rate of the specified noble In accordance with the gases is ::; 330 mCi/second. Surveillance Frequency Control Program Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a

~ 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level SUSQUEHANNA - UNIT 1 TS I 3.7-14 Amendment ~ 266 /

Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each required main In accordance with the turbine bypass valve. Surveillance Frequency Control Program SR 3.7.6.2 Perform a system functional test. In accordance with the Surveillance Frequency Control Program SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM In accordance with the RESPONSE TIME is within limits. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.7-16 Amendment 17f,, I

)-t(J,411'8, 266

Spent Fuel Storage Pool Water Level 3.7.7

3. 7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be?: 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage pool water A.1 ----------------N 0 TE-----------------

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water level is In accordance with the

?: 22 ft over the top of irradiated fuel assemblies Surveillance Frequency Control seated in the spent fuel storage pool racks. Program SUSQUEHANNA - UNIT 1 TS/ 3.7-17 Amendment ya: 266 I

Main Turbine Pressure Regulation System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify that both Main Turbine Pressure Regulators In accordance with the are each capable of controlling main steam Surveillance Frequency pressure. Control Program In accordance with the SR 3.7.8.2 Perform a system functional test. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/3.7-19 Amendment).46, 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two or more E.1 Restore at least three required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months required DGs DGs to OPERABLE status.

inoperable.

F. Required Action F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Associated Completion Time of AND Condition A, B, C, D, or E not met. F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. One or more offsite G.1 Enter LCO 3.0.3. Immediately circuits and two or more required DGs inoperable.

OR One required DG and two offsite circuits inoperable.

SURVEILLANCE REQUIREMENTS

N 0 TE-----------------------------------------------------------

Four DGs are required and a DG is only considered OPERABLE when the DG is aligned to the Class 1E distribution system. DG Surveillance Requirements have been modified to integrate the necessary testing to demonstrate the availability of DG E and ensure i1s OPERABILITY when substituted for any other DG. If the DG Surveillance Requirements, as modified by the associated Notes, are met and performed, DG E can be considered avaiable and OPERABLE when substituted for any other DG after performance of SR 3.8.1.3 and SR 3.8.1.7.

SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated pov.er In accordance with the availability for each offsite circuit. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-4 Amendment /78 2-14,266

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.2 Not Used.

SR 3. 8. 1.3 -------------------------------NOT ES-----------------------------------

1. DG loading may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.7.

5. DG E, when not aligned to the Class 1E distribution system, may satisfy this SR using the test facility.

6. A single test will satisfy this Surveillance for both units if synchronization is to the 4.16 kV ESS bus for Unit 1 for one periodic test and synchronization is to the 4.16 kV ESS bus for Unit 2 for the next periodic test.

However, if it is not possible to perform the test on Unit 2 or test performance is not required per SR 3.8.2.1, then the test shall be performed synchronized to the 4.16 kV ESS bus for Unit 1.

Verify each DG is synchronized and loaded and operates In accordance with the for~ 60 minutes at a load ~ 3600 kW and :-::; 4000 kW. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-5 Amendment VS:' 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each engine mounted day tank fuel oil level is ~ 420 In accordance with the gallons for DG A-0 and ~ 425 gallons for DG E. Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove accumulated water from each In accordance with the engine mounted day tank. Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system operates to automatically In accordance with the transfer fuel oil from the storage tanks to each engine Surveillance mounted tank. Frequency Control Program SR 3. 8. 1 .7 -------------------------------N 0 TES-----------------------------------

1. All DG starts may be preceded by an engine prelube period.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts from standby condition and In accordance with the achieves, in ~ 1 O seconds, voltage ~ 3793 V and Surveillance frequency~ 58.8, and after steady state conditions are Frequency Control reached, maintains voltage ~ 3793 V and~ 4400 V and Program frequency~ 58.8 Hz and~ 61.2 Hz.

SR 3. 8. 1.8 -------------------------------NOTE-------------------------------------

The automatic transfer of the unit power supply shall not be performed in MODE 1 or 2.

Verify automatic and manual transfer of unit power supply In accordance with the from the normal offsite circuit to the alternate offsite Surveillance circuit. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-6 Amendment 485, 266

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 8. 1.9 -------------------------------NO TE-------------------------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG rejects a load greater than or equal to its In accordance with the associated single largest post-accident load, and: Surveillance Frequency Control Program

a. Following load rejection, the frequency is ~ 64.5 Hz;

b. Within 4.5 seconds following load rejection, the voltage is ~ 3760 V and ~ 4560 V, and after steady state conditions are reached, maintains voltage ~ 3793 V and ~ 4400 V; and

c. Within 6 seconds following load rejection, the frequency is~ 58.8 Hz and~ 61.2 Hz.

SR 3.8.1.10 ------------------------------NOTES------------------------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG does not trip and voltage is maintained In accordance with the

~ 4560 V during and following a load rejection of Surveillance

~4000 kW. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-7 Amendment ~266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.11 -------------------------------NOTES-----------------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

3. This SuNeillance shall not be performed in MODE 1, 2 or 3.

Verify on an actual or simulated loss of offsite power In accordance with the signal: Surveillance Frequency Control Program

a. De-energization of 4.16 kV ESS buses;

b. Load shedding from 4.16 kV ESS buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in s 1O seconds,

2. energizes auto-connected shutdown loads through individual load timers,

3. maintains steady state voltage ~ 3793 V and s4400V,

4. maintains steady state frequency ~ 58.8 Hz and s 61.2 Hz, and

5. supplies permanently connected loads for

~ 5 minutes.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-8 Amendment :1J6, 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.12 ------------------------------NOTES------------------------------------

1. All DG starts may be preceded by an engine prelube period.

2. DG E, when not aligned to the Class 1E distribution system, may satisfy this SR for both units by performance of SR 3.8.1.12.a, b and c using the test facility to simulate a 4.16 kV ESS bus. SR 3.8.1.12.d and e may be satisfied with either the normally aligned DG or DG E aligned to the Class 1E distribution system.

In accordance with the Surveillance Frequency Control Program Verify, on an actual or simulated Emergency Core Cooling System (ECCS) initiation signal, each DG auto-starts from standby condition and:

a. In~ 10 seconds after auto-start achieves voltage

~ 3793 V, and after steady state conditions are reached, maintains voltage ~ 3793 V and ~ 4400 V;

b. In ~ 10 seconds after auto-start achieves frequency

~ 58.8 Hz, and after steady state conditions are reached, maintains frequency~ 58.8 Hz and

~ 61.2 Hz;

c. Operates for~ 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized or auto-connected through the individual load timers from the offsite power system.

(continued)

SUSQUEHANNA - UNIT 1 TS/ 3.8-9 Amendment%, 266 I

AC Sources- Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.13 ------------------------------NOTES------------------------------------

1. A single test at the specified Frequency will satisfy this Surveillance for both units.

2. DG E, when not aligned to the Class 1E distribution system, may satisfy this SR for both units by using a simulated ECCS initiation signal.

Verify each DG's automatic trips are bypassed on actual In accordance with the or simulated loss of voltage signal on the 4.16 kV ESS bus Surveillance concurrent with an actual or simulated ECCS initiation Frequency Control signal except: Program

a. Engine overspeed; and

b. Generator differential current; and

c. Low lube oil pressure.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-10 Amendment ).J8', 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.14 ------------------------------NOTES------------------------------------

1. Momentary transients outside the load ranges do not invalidate this test.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

3. DG E, when not aligned to the Class 1E distribution system may satisfy this SR by using the test facility.

Verify each DG operates for z 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: In accordance with the Surveillance Frequency Control Program

a. For z 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded z 4400 kW ands 4700 kW for DGs A through D and z 5000 kW and s 5500 kW for DG E; and

b. For the remaining hours of the test loaded z 3600 kW and s 4000 kW for DGs A through D and z 4500 kW and s 5000 kW for DG E.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-11 Amendment 1}8, 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.15 ------------------------------NOTES------------------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated

~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded ~ 3800 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

3. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts and achieves, in ~ 1O seconds, In accordance with the voltage ~ 3793 V and frequency~ 58.8 and after steady Surveillance state conditions are reached, maintains voltage~ 3793 V Frequency Control and~ 4400 V and frequency~ 58.8 Hz and~ 61.2 Hz.

Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-12 Amendment~ 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.16 ------------------------------NOTES------------------------------------

This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

Verify each DG: In accordance with the Surveillance Frequency Control Program

a. Synchronizes with offsite power sourre while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power sourre; and

c. Returns to ready-to-load operation.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-13 Amendment V8';' 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 ------------------------------NOTES------------------------------------

This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

Verify with a DG operating in test mode and connected to In accordance with the its bus, an actual or simulated ECCS initiation signal Surveillance overrides the test mode by: Frequency Control Program

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 ------------------------------NOTE--------------------------------------

Load timers associated with equipment that has automatic initiation capability disabled are not required to be OPERABLE.

Verify each sequenced load is within required limits of the In accordance with the design interval. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-14 Amendment :1.1-8;" 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.19 ------------------------------NOTES------------------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

3. This SuNeillance shall not be performed in MODE 1, 2 or 3.

Verify on an actual or simulated loss of offsite power In accordance with the signal in conjunction with an actual or simulated ECCS Surveillance initiation signal: Frequency Control Program

a. De-energization of 4.16 kV ESS buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in s 10 seconds,

2. energizes auto-connected emergency loads through individual load timers,

3. achieves steady state voltage ~ 3793 V and s 4400V,

4. achieves steady state frequency ~ 58.8 Hz and s 61.2 Hz, and

5. supplies permanently connected and auto-connected emergency loads for~ 5 minutes.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-15 Amendment m, 266 I

AC Sources - Operating 3.8.1 3.8 Electrical Power Systems SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 8. 1.2 0 ------------------------------NO TES------------------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR does not have to be performed with DG E substituted for any DG.

Verify, when started simultaneously from standby In accordance with the condition, each DG achieves, in~ 10 seconds, voltage Surveillance z 3793 V and frequency z 58.8 and after steady state Frequency Control conditions are reached, maintains voltage z 3793 V and Program

~ 4400 V and frequency z 58.8 Hz and~ 61.2 Hz.

SUSQUEHANNA - UNIT 1 TS/ 3.8-16 Amendment j..18: 266

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains In accordance with the

?: 47,570 gallons for DG A-D; Surveillance

?: 60,480 gallons for DG E. Frequency Control Program SR 3.8.3.2 Verify lube oil sump level is visible in the sight glass. In accordance with the Surveillance Frequency Control Program SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil are In accordance with tested in accordance with, and maintained within the limits the Diesel Fuel Oil of, the Diesel Fuel Oil Testing Program. Testing Program SR 3. 8. 3. 4 -------------------------------N 0 TE-------------------------------------

Not required to be met when DG is operating.

Verify each DG air start receiver pressure is :?: 240 psig. In accordance with the Surveillance Frequency Control Program SR 3.8.3.5 Check for and remove accumulated water from each fuel In accordance with the oil storage tank. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.8-22 Amendment 4-78, J.83, 266 I

DC Sources-Operating 3.8.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Diesel Generator E DC E.1 Verify that all ESW valves 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power associated with Diesel subsystem inoperable, Generator E are closed.

when not aligned to the Class 1E distribution system.

F. Diesel Generator E DC F.1 Declare Diesel Generator E 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power inoperable.

subsystem inoperable, when aligned to the Class 1E distribution system.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or equal to In accordance with the the minimum established float voltage. Surveillance Frequency Control Program SR 3.8.4.2 Verify each required battery charger supplies its In accordance with the associated battery at the following rates for~ 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at Surveillance greater than or equal to the minimum established float Frequency Control voltages. Program

a. ~ 100 amps for the 125V Battery

b. ~ 300 amps for the 250V Battery

c. ~ 200 amps for the 125V Diesel Generator E Battery (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-24 Amendment 4-78, ~ . .248: 266 I

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 8 .4. 3 ---------------------------------NO TES---------------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not be Performed in Mode 1, 2, or 3 except for the Diesel Generator E DC electrical power subsystem. This Surveillance can be performed on the Diesel Generator E DC electrical power subsystem when the Diesel Generator E is not aligned to the Class 1 E distribution system. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and maintain In accordance with the in OPERABLE status, the required emergency loads for Surveillance the design duty cycle when subjected to a battery service Frequency Control test. Program SUSQUEHANNA - UNIT 1 TS/ 3.8-25 Amendment t=ffl, 235, 238: 266 I

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1

N 0 TE----------------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is :::; 2 amps. In accordance with the Surveillance Frequency Control Program SR 3.8.6.2 Verify each battery pilot cell voltage is ;::.: 2.07 V. In accordance with the Surveillance Frequency Control Program SR 3.8.6.3 Verify each battery connected cell electrolyte level is In accordance with greater than or equal to minimum established design the Surveillance limits. Frequency Control Program SR 3.8.6.4 Verify each battery pilot cell temperature is greater than or In accordance with equal to minimum established design limits. the Surveillance Frequency Control Program SR 3.8.6.5 Verify each battery connected cell voltage is ?: 2.07 v. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 1 TS I 3.8-35 Amendment 4-78, ~ 266 I

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 8. 6. 6 ---------------------------------NO TE-----------------------------------

Th is Surveillance shall not be Performed in Mode 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is ~ 80% of the manufacturer's In accordance with rating when subjected to a performance discharge test or the Surveillance a modified performance discharge test. Frequency Control Program 12 months when battery shows degradation or has reached 85% of expected service life with capacity

< 100% of manufacturer's rating 24 months when battery has reached 85% of the expected service life with capacity

~ 100% of manufacturer's rating SUSQUEHANNA - UNIT 1 TS I 3.8-36 Amendment -i.78, ~. 266 I

Distribution Systems - Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8. 7 .1 Verify correct breaker alignments and voltage or In accordance with indicated power availability to required AC and DC the Surveillance electrical power distribution subsystems. Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.8-39 AmendmenU-7-8; 266 I

Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Diesel Generator E B.1 Verify that all ESW valves 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power associated with Diesel distribution Generator E are closed.

subsystem inoperable, while not aligned to the Class 1E distribution system.

C. Diesel Generator E C.1 Declare Diesel Generator E 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DC electrical power inoperable.

distribution subsystem inoperable, while aligned to the Class 1E distribution system.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage or In accordance with indicated power availability to required AC and DC the Surveillance electrical power distribution subsystems. Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.8-43 Amendment )Ja:'266 I

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each In accordance with the of the following required refueling equipment Surveillance Frequency interlock inputs: Control Program

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform frame mounted hoist, fuel loaded,

e. Refuel platform monorail mounted hoist, fuel loaded.

SUSQUEHANNA - UNIT 1 TS I 3.9-2 Amendment _pB, 266 I

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Refuel position one-rod-out A.1 Suspend control rod Immediately interlock inoperable. withdrawal.

A.2 Initiate action to fully insert all Immediately insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in Refuel In accordance with the position. Surveillance Frequency Control Pro ram (continued)

SUSQUEHANNA - UNIT 1 TS I 3.9-3 Amendment 1J8;"'266 I

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 9.2. 2 -----------------------------NOTE-----------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.9-4 Amendment ~266 I

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rods not A.1 Suspend loading fuel Immediately fully inserted. assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.9-5 Amendment !J8, 266 I

Control Rod OPERABILITY-Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION Tl ME A One or more withdrawn A.1 Initiate action to fully insert Immediately control rods inoperable. inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 9. 5. 1 -----------------------------NOTE-----------------------------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one In accordance with the notch. Surveillance Frequency Control Proaram SR 3.9.5.2 Verify each withdrawn control rod scram In accordance with the accumulator pressure is~ 940 psig. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.9-8 Amendment 1J8'; 266 I

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be~ 22 ft above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new or irradiated fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not within A.1 Suspend movement of fuel Immediately limit. assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is~ 22 ft above the top of In accordance with the the RPV flange. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.9-9 Amendment jAr, 266 I

RHR-High Water Level 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is In accordance with the operating. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.9-12 Amendment j,R(, 266 I

RHR - Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is In accordance with the operating. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.9-15 Amendment y.a;'266 I

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

OR A. 3. 2 ------------NOTE------------

On ly applicable in MODE5 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted in core cells In accordance with the containing one or more fuel assemblies. Surveillance Frequency Control Program SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. In accordance with the Surveillance Frequency Control Proqram SUSQUEHANNA - UNIT 1 TS/ 3.10-5 Amendment ~266 I

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS FREQUENCY SURVEILLANCE SR 3.10.3.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.3.2 ----------------------------NOTE------------------------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the control rod In accordance with the being withdrawn, in a five by five array centered Surveillance Frequency on the control rod being withdrawn, are disarmed. Control Program SR 3.10.3.3 Verify all control rods other than the control rod In accordance with the being withdrawn, are fully inserted. Surveillance Frequency Control Prooram SUSQUEHANNA - UNIT 1 TS/3.10-8 Amendment j,.]8, 266 I

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the above B.1 Suspend withdrawal of Immediately requirements not met with the control rod and the affected control rod not removal of associated insertable. CRD.

B.2.1 Initiate action to fully Immediately insert all control rods.

B.2.2 Initiate action to Immediately satisfy the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.4.2 ----------------------------NOTE------------------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the control rod In accordance with the being withdrawn, in a five by five array centered Surveillance Frequency on the control rod being withdrawn, are Control Program disarmed.

(continued)

SUSQUEHANNA - UNIT 1 TS I 3.10-11 Amendment *. 266 I

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the control rod In accordance with the being withdrawn, are fully inserted. Surveillance Frequency Control Proaram SR 3.10.4.4 -----------------------------NOTE-----------------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is inserted. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/3.10-12 Amendment~ 266 I

Single CRD Removal - Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to fully Immediately insert all control rods.

A.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod In accordance with the withdrawn for the removal of the associated CRD, Surveillance Frequency are fully inserted. Control Program SR 3.10.5.2 Verify all control rods, other than the control rod In accordance with the withdrawn for the removal of the associated CRD, Surveillance Frequency in a five by five array centered on the control rod Control Program withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is inserted. In accordance with the Surveillance Frequency Control Program SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 (continued)

SUSQUEHANNA - UNIT 1 TS/3.10-14 Amendment jJ8; 266 I

Single CRD Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no CORE ALTERATIONS are in progress. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.10-15 Amendment~. 266 I

Multiple Control Rod Withdrawal - Refueling 3.10.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to fully Immediately insert all control rods in core cells containing one or more fuel assemblies.

A.3.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed from In accordance with the core cells associated with each control rod or Surveillance Frequency CRD removed. Control Program SR 3.10.6.2 Verify all other control rods in core cells containing In accordance with the one or more fuel assemblies are fully inserted. Surveillance Frequency Control Proqram SR 3.10.6.3 -----------------------------NOTE-----------------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in In accordance with the compliance with an approved reload sequence. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS/3.10-17 Amendment J,.78, 266 I

SOM Test- Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.2 ----------------------------NOTE-----------------------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for LCO According to the applicable 3.3.2.1. Function 2 of Table 3.3.2.1-1. SRs SR 3.10.8.3 ----------------------------NOTE-----------------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in compliance During control rod movement with the approved control rod sequence for the SOM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in In accordance with the progress. Surveillance Frequency Control Prooram (continued)

SUSQUEHANNA - UNIT 1 TS I 3.10-22 Amendment 1A(266 I

SOM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not go to Each time the control rod is the withdrawn overtravel position. withdrawn to "full out" position Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure In accordance with the

~940 psig Surveillance Frequency Control Program SUSQUEHANNA - UNIT 1 TS I 3.10-23 Amendment VS, 266 I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program (continued)

e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of OBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

5.5.15 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

SUSQUEHANNA - UNIT 1 TS I 5.0-18C Amendment 282, 266 I

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SUSQUEHANNA NUCLEAR. LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 247 Renewed License No. NPF-22

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for the amendment filed by Susquehanna Nuclear, LLC, dated October 27, 2014, as supplemented by letters dated July 2, 2015; September 21, 2015; November 11, 2015; and January 29, 2016, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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.

Enclosure 2

2. Accordingly, the license is amended by changes to the Renewed Facility Operating License as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of the Renewed Facility Operating License No. NPF-22 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 247, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. The license amendment is effective as of its date of issuance and shall be implemented within 180 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 1/

J. *~

~/\./'--~

/")r'v- /

J' ,-f, ,,---

Douglas ~. Broaddus, C~ief I/ ~

Plant Licensing Branch 1-2

Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: May 20, 2016

ATTACHMENT TO LICENSE AMENDMENT NO. 247 RENEWED FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following page of the Renewed 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 INSERT 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 INSERT TS I 3.1-10 TS I 3.1-10 TS/3.1-13 TS I 3.1-13 TS I 3.1-17 TS/3.1-17 TS/3.1-19 TS I 3.1-19 TS/3.1-21 TS I 3.1-21 TS I 3.1-22 TS I 3.1-22 TS I 3.1-26 TS I 3.1-26 TS I 3.2-2 TS I 3.2-2 TS I 3.2-4 TS I 3.2-4 TS I 3.2-6 TS I 3.2-6 TS I 3.3-3 TS I 3.3-3 TS I 3.3-4 TS I 3.3-4 TS I 3.3-5 TS I 3.3-5 TS I 3.3-6 TS I 3.3-6

TS I 3.3-6a

TS I 3.3-6b TS I 3.3-12 TS/3.3-12 TS/3.3-13 TS I 3.3-13 TS I 3.3-18 TS I 3.3-18

REMOVE INSERT TS/3.3-19 TS I 3.3-19 TS I 3.3-22 TS I 3.3-22 TS I 3.3-24 TS I 3.3-24 TS I 3.3-25 TS I 3.3-25 TS I 3.3-28 TS I 3.3-28 TS I 3.3-32 TS I 3.3-32 TS I 3.3-33 TS I 3.3-33 TS I 3.3-35 TS I 3.3-35 TS I 3.3-36 TS I 3.3-36 TS I 3.3-42 TS I 3.3-42 TS I 3.3-50 TS I 3.3-50 TS I 3.3-55 TS I 3.3-55 TS I 3.3-56 TS I 3.3-56 TS I 3.3-65 TS I 3.3-65 TS I 3.3-70 TS I 3.3-70 TS I 3.3-73 TS I 3.3-73 TS I 3.3-76 TS I 3.3-76 TS I 3.3-77 TS I 3.3-77 TS I 3.4-3 TS I 3.4-3 TS I 3.4-7 TS I 3.4-7 TS I 3.4-11 TS I 3.4-11 TS I 3.4-16 TS I 3.4-16 TS I 3.4-18 TS I 3.4-18 TS I 3.4-21 TS I 3.4-21 TS I 3.4-23 TS I 3.4-23 TS I 3.4-26 TS I 3.4-26 TS I 3.4-28 TS I 3.4-28 TS I 3.4-29 TS I 3.4-29 TS I 3.4-31 TS I 3.4-31 TS I 3.5-4 TS I 3.5-4 TS I 3.5-6 TS I 3.5-6 TS I 3.5-7 TS I 3.5-7

REMOVE INSERT TS/ 3.5-9 TS/ 3.5-9 TS/ 3.5-10 TS/ 3.5-10 TS/ 3.5-11 TS I 3.5-11 TS/ 3.5-13 TS/3.5-13 TS/ 3.5-14 TS/ 3.5-14 TS/ 3.6-3 TS/ 3.6-3 TS/ 3.6-7 TS/ 3.6-7 TS/ 3.6-12 TS/ 3.6-12 TS/ 3.6-13 TS/ 3.6-13 TS/ 3.6-14 TS/ 3.6-14 TS/ 3.6-17 TS/ 3.6-17 TS/ 3.6-18 TS/3.6-18 TS/ 3.6-20 TS/ 3.6-20 TS/ 3.6-21 TS/ 3.6-21 TS/ 3.6-24 TS/ 3.6-24 TS/ 3.6-25 TS/ 3.6-25 TS/ 3.6-27 TS/ 3.6-27 TS/ 3.6-29 TS/ 3.6-29 TS/ 3.6-33 TS/ 3.6-33 TS/ 3.6-34 TS/ 3.6-34 TS/ 3.6-36 TS/ 3.6-36 TS/ 3.6-37 TS/ 3.6-37 TS/ 3.6-41 TS/ 3.6-41 TS/ 3.6-44 TS/ 3.6-44 TS/ 3.7-3 TS/ 3.7-3 TS/ 3.7-3a TS/ 3.7-3a TS/ 3.7-5 TS/ 3.7-5 TS/ 3.7-8 TS/ 3.7-8 TS/ 3.7-12 TS/ 3.7-12 TS/ 3.7-14 TS/ 3.7-14 TS/ 3.7-16 TS/ 3.7-16 TS/ 3.7-17 TS/3.7-17

REMOVE INSERT TS/ 3.7-19 TS/ 3.7-19 TS/ 3.8-6 TS/ 3.8-6 TS/ 3.8-7 TS/ 3.8-7 TS/ 3.8-8 TS/ 3.8-8 TS/ 3.8-9 TS/ 3.8-9 TS/ 3.8-10 TS/3.8-10 TS I 3.8-11 TS/ 3.8-11 TS/ 3.8-12 TS/ 3.8-12 TS/ 3.8-13 TS/ 3.8-13 TS/ 3.8-14 TS/ 3.8-14 TS/3.8-15 TS/3.8-15 TS/ 3.8-16 TS/ 3.8-16 TS/ 3.8-17 TS/3.8-17 TS/ 3.8-18 TS/ 3.8-18 TS/ 3.8-25 TS/ 3.8-25 TS/ 3.8-28 TS/ 3.8-28 TS/ 3.8-29 TS/ 3.8-29 TS/ 3.8-42 TS/ 3.8-42 TS/ 3.8-43 TS/ 3.8-43 TS/ 3.8-47 TS/ 3.8-47 TS/ 3.8-53 TS/ 3.8-53 TS/ 3.9-2 TS/ 3.9-2 TS/ 3.9-3 TS/ 3.9-3 TS/ 3.9-4 TS/ 3.9-4 TS/ 3.9-5 TS/ 3.9-5 TS/ 3.9-8 TS/ 3.9-8 TS/ 3.9-9 TS/ 3.9-9 TS/ 3.9-12 TS/ 3.9-12 TS/ 3.9-15 TS/3.9-15 TS/ 3.10-5 TS/ 3.10-5 TS/ 3.10-8 TS/ 3.10-8 TS I 3.10-11 TS/ 3.10-11

REMOVE INSERT TS I 3.10-12 TS I 3.10-12 TS I 3.10-14 TS I 3.10-14 TS I 3.10-15 TS I 3.10-15 TS I 3.10-17 TS I 3.10-17 TS I 3.10-22 TS I 3.10-22 TS I 3.10-23 TS I 3.10-23 TS I 5.0-18C TS I 5.0-18C

(3) Susquehanna Nuclear, LLC, 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 neutron sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Susquehanna Nuclear, LLC, 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) Susquehanna Nuclear, LLC, pursuant to the Act and 10 CFR Parts 30, 40, 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 license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level Susquehanna Nuclear, LLC is authorized to operate the facility at reactor core power levels not in excess of 3952 megawatts thermal in accordance with the conditions specified herein. The preoperational test, startup tests and other items identified in License Conditions 2.C.(20), 2.C.(21), 2.C.(22), and 2.C.(23) to this license shall be completed as specified.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 247, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. Susquehanna Nuclear, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

For Surveillance Requirements (SRs) that are new in Amendment 151 to Facility Operating License No. NPF-22, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 151. For SRs that existed prior to Amendment 151, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 151.

Renewed Operating License No. NPF-22 Amendment No. 247

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. In accordance with the Surveillance Frequency Control Program SR 3.1.3.2 NOT USED SR 3. 1.3. 3 ----------------------------N 0 TE----------------------------

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each withdrawn control rod at least one In accordance with the notch. Surveillance Frequency Control Program SR 3.1.3.4 Verify each control rod scram time from fully In accordance with withdrawn to notch position 05 is ::::: 7 seconds. SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 (continued)

SUSQUEHANNA - UNIT 2 TS/3.1-10 Amendment .+M, 22-9, 247 I

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested In accordance with the control rod scram time is within the limits of Surveillance Frequency Table 3.1.4-1 with reactor steam dome pressure Control Program 2 800 psig.

SR 3.1.4.3 Verify each affected control rod scram time is Prior to declaring control rod within the limits of Table 3.1.4-1 with any reactor OPERABLE after work on steam dome pressure. control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is Prior to exceeding 40% RTP within the limits of Table 3.1.4-1 with reactor after fuel movement within steam dome pressure 2 800 psig. the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time SUSQUEHANNA - UNIT 2 TS I 3.1-13 Amendment 4-M, 244, 2-2-8, 247 I

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more control rod C.1 Verify all control rods Immediately upon scram accumulators associated with inoperable discovery of charging inoperable with reactor accumulators are fully water header steam dome pressure inserted. pressure < 940 psig

< 900 psig.

AND C.2 Declare the associated control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod inoperable.

D. Required Action and D.1 ----------------N 0 TE---------------

associated Completion Not applicable if all inoperable Time of Required Action control rod scram B.1 or C.1 not met. accumulators are associated with fully inserted control rods.

Place the reactor mode switch Immediately in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator In accordance with the nitrogen pressure is ;::=: 940 psig. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.1-17 Amendment 1-M, 247 I

Rod Pattern Control 3.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION Tl ME B. Nine or more OPERABLE B.1 --------------NOTE-------------------

control rods not in Rod worth minimizer (RWM) compliance with BPWS. may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal of control Immediately rods.

B.2 Place the reactor mode switch 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with In accordance with the BPWS. Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 2 TS/3.1-19 Amendment 1-6-1, 247 I

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate In accordance with the solution is within the limits of Figure 3.1. 7-1. Surveillance Frequency Control ProQram SR 3.1.7.2 Verify temperature of sodium pentaborate solution In accordance with the is within the limits of Figure 3.1.7-2. Surveillance Frequency Control Prooram SR 3.1.7.3 Verify temperature of pump suction piping is within In accordance with the the limits of Figure 3.1.7-2. Surveillance Frequency Control Program SR 3.1.7.4 Verify continuity of explosive charge. In accordance with the Surveillance Frequency Control ProQram SR 3.1.7.5 Verify the concentration of sodium pentaborate in In accordance with the solution is within the limits of Figure 3.1.7-1. Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 (continued)

SUSQUEHANNA - UNIT 2 TS I 3.1-21 Amendment 1fj1, W, 247 /

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify each SLC subsystem manual and power In accordance with the operated valve in the flow path that is not locked, Surveillance Frequency sealed, or otherwise secured in position is in the Control Program correct position, or can be aligned to the correct position.

SR 3.1.7.7 Verify each pump develops a flow rate~ 40.0 gpm In accordance with the at a discharge pressure~ 1250 psig. lnservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem pump into In accordance with the reactor pressure vessel. Surveillance Frequency Control Program SR 3.1.7.9 Verify all heat traced piping between storage tank In accordance with the and pump suction is unblocked. Survellance Frequency Control Program Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 SR 3.1. 7.10 Verify sodium pentaborate enrichment is ~ 88 Prior to addition to SLC tank.

atom percent B-10.

SUSQUEHANNA - UNIT 2 TS/ 3.1-22 Amendment 1 sjl, 1¢3, m, 247 I

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 -----------------------------NOTE-----------------------------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

In accordance with the Verify each SDV vent and drain valve is open.

Surveillance Frequency Control Program SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully In accordance with the closed and fully open position.

Surveillance Frequency Control Program In accordance with the SR 3.1.8.3 Verify each SDV vent and drain valve: Surveillance Frequency Control Program

a. Closes in ::; 30 seconds after receipt of an actual or simulated scram signal; and

b. Opens when the actual or simulated scram signal is reset.

SUSQUEHANNA - UNIT 2 TS/ 3.1-26 Amendment ~247 I

APLHGR 3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to the Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after limits specified in the COLR. ~ 23% RTP In accordance with the Surveillance Frequency Control Program Prior to exceeding 44% RTP SUSQUEHANNA - UNIT 2 TS I 3.2-2 Amendment 1-51,,22<.247 I

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after limits specified in the COLR. ~ 23% RTP AND In accordance with the Surveillance Frequency Control Program Prior to exceeding 44% RTP SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SRs in 3.1.4 SUSQUEHANNA - UNIT 2 TS I 3.2-4 Amendment 181, ~* 24 7 I

LHGR 3.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after limits specified in the COLR. ~ 23% RTP In accordance with the Surveillance Frequency Control Program Prior to exceeding 44% RTP SUSQUEHANNA - UNIT 2 TS I 3.2-6 Amendment 1-81, ~ 24 7 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

NOTES---------------------------------------------------------

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.3 -------------------------------NOTE-----------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER;;::: 23% RTP.

Verify the absolute difference between the average power In accordance range monitor (APRM) channels and the calculated power with the is $ 2% RTP while operating at;;::: 23% RTP. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.3-3 Amendment +a+, ~. 22G, 224,247

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.4 -------------------------------NOTE-----------------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.6 Verify the source range monitor (SRM) and intermediate Prior to fully range monitor (IRM) channels overlap. withdrawing SRMs from the core.

SR 3.3.1.1.7 ---------------------------------N 0 TE---------------------------------

0 nly required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.8 Calibrate the local power range monitors. In accordance with the Surveillance Frequency Control ProQram (continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-4 Amendment +a-1-, 224, 247 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.9 ---------------------------------N 0 TE---------------------------------

A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.10 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.11 ---------------------------------N 0 TES-------------------------------

1. Neutron detectors are excluded.

2. For Function 1.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.3-5 Amendment 4-a+, W7,-224; 247 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.12 ---------------------------------N 0 TES-------------------------------

1. For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.13 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.14 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-6 Amendment4-W, 207, ~ 247 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and Turbine Control In accordance with Valve Fast Closure, Trip Oil Pressure-Low Functions the Surveillance are not bypassed when THERMAL POWER is Frequency Control

~26% RTP. Program SR 3.3.1.1.17 ----------------------------NOTES------------------------------

1. Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within limits. In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.18 --------------------------------N 0 TES------------------------------

1. Neutron detectors are excluded.

2. For Functions 2b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM Simulated In accordance with Thermal Power is <= 25% and recirculation drive flow is ::; the Surveillance value equivalent to the core flow value defined in the Frequency Control COLR. Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.3-6a Amendment 24 7 I

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.3.1.1.20 Adjust recirculation drive flow to conform to reactor core In accordance with flow. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-6b Amendment 24 7 I

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS

N 0 TE-----------------------------------------------------------

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2 --------------------------------N 0 TES--------------------------------

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is located in: In accordance with the Surveillance Frequency Control Program

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.3-12 Amendment '.L.5-t;"'247 I

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.4 --------------------------------NOTE--------------------------------

N ot required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS

a. ~ 3.0 cps if a signal to noise ratio~ 2:1 or In accordance with the Surveillance Frequency Control Program

b. Within the limits of Figure 3.3.1.2-1 SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST and determination of In accordance with the signal to noise ratio. Surveillance Frequency Control Program SR 3.3.1.2.6 ---------------------------------NOTE--------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST and determination of In accordance with the signal to noise ratio. Surveillance Frequency Control Program SR 3.3.1.2.7 ---------------------------------NOTES----------------------------

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.3-13 Amendment jM, 247 I

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

NOTES-----------------------------------------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3. 3. 2 .1 .2 ----------------------------------NOTE------------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at::; 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3. 3. 2. 1.3 ----------------------------------N 0 TE-------------------------------------

N ot required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is::; 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.1.4 Verify the RBM:

a. Low Power Range - Upscale Function is not bypassed when APRM In accordance with the Simulated Thermal Power is ~ 28% RTP and :> Intermediate Power Surveillance Range Setpoint specified in the COLR. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-18 Amendment :1-61, 2ff7, ?-2Q, 247 I

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

b. Intermediate Power Range- Upscale Function is not bypassed when APRM Simulated Thermal Power is> Intermediate Power Range Setpoint specified in the COLR and:-::;; High Power Range Setpoint specified in the COLR.

c. High Power Range - Upscale Function is not bypassed when APRM Simulated Thermal Power> High Power Range Setpoint specified in the COLR.

SR 3.3.2.1.5 Verify the RWM is not bypassed when THERMAL POWER In accordance with is~ 10% RTP. the Surveillance Frequency Control Program SR 3. 3. 2 .1 .6 -----------------------------------NOTE---------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

In accordance with Perform CHANNEL FUNCTIONAL TEST. the Surveillance Frequency Control Program SR 3.3.2.1. 7 ------------------------------------NOTE----------------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.2.1.8 Verify control rod sequences input to the RWM are in Prior to declaring conformance with BPWS. RWM OPERABLE following loading of sequence into RWM SUSQUEHANNA - UNIT 2 TS/ 3.3-19 Amendment 1-51, .22(), 247 I

Feedwater- Main Turbine High Water Level Trip Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS

NOTE-----------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided feedwater - main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.2

1. A test of all required contacts does not have to be performed.

2. For the Feedwater - Main Turbine High Water Level Function, a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.2.3 Perform CHANNEL CALIBRATION. The Allowable Value In accordance with shall bes; 55.5 inches. the Surveillance Frequency Control Program SR 3.3.2.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST including In accordance with valve actuation. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-22 Amendment~ 247 I

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition referenced in Immediately associated Completion Table 3.3.3.1-1 for the channel.

Time of Condition C not met.

E. As required by E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by F.1 Initiate action in accordance with Immediately Required Action D.1 and Specification 5.6.7.

referenced in Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

N 0 TES---------------------------------------------------------

Th ese SRs apply to each Function in Table 3.3.3.1-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-24 Amendment ,t5-t, 24 7 I

PAM Instrumentation 3.3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.3.1.2 Not Used.

SR 3.3.3.1.3 Perform CHANNEL CALIBRATION for all Functions except In accordance with PCIV Position. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.3-25 Amendment t61, 241, 247 I

Remote Shutdown System 3.3.3.2 SURVEILLANCE REQUIREMENTS

N 0 TES---------------------------------------------------------

Refer to Table 3.3.3.2-1 to determine which SRs apply for each Remote Shutdown System Function.

SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.3.2.2 Verify each required control circuit and transfer switch is In accordance with capable of performing the intended function. the Surveillance Frequency Control Program SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each required In accordance with instrumentation channel. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-28 Amendment j...5-r 24 7 I

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS

NOTE-----------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.1.2 Perform CHANNEL CALIBRATION. The Allowable In accordance with Values shall be: the Surveillance Frequency Control Program TSV--Closure: ~ 7% closed; and TCV Fast Closure, Trip Oil Pressure-Low: ~ 460 psig.

SR 3.3.4.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST including In accordance with breaker actuation. the Surveillance Frequency Control Program SR 3.3.4.1.4 Verify TSV-Closure and TCV Fast Closure, Trip Oil In accordance with Pressure-Low Functions are not bypassed when the Surveillance THERMAL POWER is ~ 26% RTP. Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-32 Amendment 1-8'1, ?24'* 24 7 I

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 3. 4. 1. 5 -----------------------------------NO TE---------------------------------

Breaker arc suppression time may be assumed from the most recent performance of SR 3.3.4.1.6.

Verify the EOC-RPT SYSTEM RESPONSE TIME is In accordance with within limits. the Surveillance Frequency Control Program SR 3.3.4.1.6 Determine RPT breaker arc suppression time. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-33 Amendment%, 247 I

A TWS-RPT Instrumentation 3.3.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One Function with B.1 Restore ATWS-RPT trip capability. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months A TWS-RPT trip capability not maintained.

C. Both Functions with C.1 Restore A TWS-RPT trip capability 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip for one Function.

capability not maintained.

D. Required Action and D.1 Remove the associated 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion recirculation pump from service.

Time not met.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

NOTE---------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform CHANNEL CHECK of Reactor Vessel Water In accordance with Level, Low Low, Level 2. the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.3-35 Amendment )5t, 24 7 I

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.4.2.3 Perform CHANNEL CALIBRATION of the Reactor Steam In accordance with Dome Pressure-High. The Allowable Values shall be the Surveillance

~ 1150 psig. Frequency Control Program SR 3.3.4.2.4 Perform CHANNEL CALIBRATION of the Reactor Vessel In accordance with Water Level Low Low, Level 2. The Allowable Values the Surveillance shall be ~ - 45 inches. Frequency Control Program SR 3.3.4.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST including In accordance with breaker actuation. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-36 Amendment j,51, 247 I

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------------------------

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.e; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c and 3.e provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.3-42 Amendment ~. 202, 247

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS

N 0 TES-------------------------------------------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 4 and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than Functions 2 and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-50 Amendment ~24 7 I

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

N 0 TES----------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.2 1. A test of all required contacts does not have to be performed

2. For Functions 2.e, 3.a, and 4.a, a test of all required relays does not have to be performed Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6 .1.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Proqram SR 3.3.6.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Proqram SUSQUEHANNA - UNIT 2 TS I 3.3-55 Amendment :J.,31, 247 I

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.3.6.1.6 ---------------------------NOTE-----------------------------

1. For Function 1.b. channel sensors are excluded.

2. Response time testing of isolating relays is not required for Function 5.a.

Verify the ISOLATION SYSTEM RESPONSE TIME In accordance with is within lirrits. the Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 2 TS I 3.3-56 Amendment 1-6{), 24 7 I

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS

N 0 TES-------------------------------------------------------

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.2 A test of all required contacts does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-65 Amendment :1..51: 24 7 I

CREOAS System Instrumentation 3.3.7.1 ACTIONS SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------------------------

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREOAS Function.

2. When a channel is placed in an inoperable status solely for perfonnance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains CREOAS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2

1. A test of all required contacts does not have to be perfonned.

2. For Function 8, a test of all required relays does not have to be performed.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.4 Perfonn CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-70 Amendment j_5.t, 24 7 I

LOP Instrumentation 3.3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Restore the inoperable Channel. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action A.1 and referenced in Table 3.3.8.1-1.

E. Required Action and E.1 Declare associated diesel generator Immediately associated Completion (DG) inoperable.

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

SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------------------------

1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains DG initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.2 Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.3-73 Amendment .JS1 ,J.08: 247 I

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully insert all Immediately associated Completion insertable control rods in core cells Time of Condition A containing one or more fuel or B not met in assemblies.

MODE4 or5.

D.2.1 Initiate action to restore one Immediately electric power monitoring assembly to OPERABLE status for inservice power supply(s) supplying required instrumentation.

D.2.2 Initiate action to isolate the Immediately Residual Heat Removal Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3 .3 .8. 2 . 1 ---------------------------------N 0 TE--------------------------------------

0 nly required to be performed prior to entering MODE 2 or 3 from MODE 4, when in MODE 4 for ~ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.3-76 Amendment~ 247 I

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The Allowable In accordance with Values shall be: the Surveillance Frequency Control Program

a. Overvoltage ~ 129.1 V for Division A and~ 130.3 V for Division B.

b. Undervoltage ~ 112.0 V for Division A and~ 112.5 V for Division B.

c. Underfrequency ~ 57 Hz.

SR 3.3.8.2.3 Perform a system functional test. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.3-77 Amendment 121. 247 I

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 --------------------------NOTE---------------------------

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify recirculation loop jet pump flow In accordance with the mismatch with both recirculation loops in Surveillance Frequency operation is: Control Program

a. :::; 10 million lbm/hr when operating at

< 75 million lbm/hr total core flow; and

b. :::; 5 million lbm/hr when operating at

75 million lbm/hr total core flow.

SR 3.4. 1.2 --------------------------NOTE---------------------------

On ly required to be met during single loop operations.

In accordance with the Verify recirculation pump speed is within the Surveillance Frequency limit specified in the LCO. Control Program SUSQUEHANNA - UNIT 2 TS 13.4-3 Amendment 151,

-t5fr, t98, ~' 247

Jet Pumps 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4. 2. 1 --------------------------NOTES-------------------------

1. Not required to be completed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2. Not required to be completed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after> 23% RTP.

Verify at least two of the following criteria (a, In accordance with the b, or c) are satisfied for each operating Surveillance Frequency recirculation loop: Control Program

a. Recirculation loop drive flow versus Recirculation Pump speed differs by

~ 10% from established patterns.

b. Recirculation loop drive flow versus total core flow differs by ~ 10% from established patterns.

c. Each jet pump diffuser to lower plenum differential pressure differs by

~ 20% from established patterns, or each jet pump flow differs by~ 10%

from established patterns.

SUSQUEHANNA - UNIT 2 TS/ 3.4-7 Amendment 'J..81, ,?24, 24 7 I

RCS Operational LEAKAGE 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify source of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months unidentified LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE In accordance with the and unidentified LEAKAGE increases are Surveillance Frequency within limits. Control Program SUSQUEHANNA - UNIT 2 TS/ 3.4-11 Amendment ~247 I

RCS Leakage Detection Instrumentation 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Perform a CHANNEL CHECK of required primary In accordance with containment atmospheric monitoring system. the Surveillance Frequency Control Program SR 3.4.6.2 Perform a CHANNEL FUNCTIONAL TEST of required In accordance with leakage detection instrumentation. the Surveillance Frequency Control Proqram SR 3.4.6.3 Perform a CHANNEL CALIBRATION of required In accordance with leakage detection instrumentation. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.4-16 Amendment J.61, 247 I

RCS Specific Activity 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 --------------------------N 0 TE-------------------------

0 n ly required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT In accordance with 1-131 specific activity is~ 0.2 µCi/gm. the Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 2 TS/3.4-18 Amendment~ 247 I

RHR Shutdown Cooling System - Hot Shutdown 3.4.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 ----------------------------N 0 TE------------------------

N ot required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify one RHR shutdown cooling subsystem or In accordance with the recirculation pump is operating. Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 2 TS I 3.4-21 Amendment j,51, 247 I

RHR Shutdown Cooling System-Cold Shutdown 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown cooling B.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation. circulating by an alternate of no reactor coolant method. circulation No recirculation pump in operation. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify one RHR shutdown cooling subsystem or In accordance with the recirculation pump is operating. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.4-23 Amendment _is-<.247 I

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 -----------------------------NOTE--------------------------------

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a. RCS pressure and RCS temperature are to In accordance with the the right of the most limiting curve specified Surveillance Frequency in Figures 3.4.10-1 through 3.4.10-3; and Control Program

b. -------------------N 0 TE--------------------------------

0 n ly applicable when governed by Figure 3.4.10-2, Curve B, and Figure 3.4.10-3, Curve C.

RCS heatup and cooldown rates are

~ 100°F in any one hour period; and

c. ------------------------N 0 TE--------------------------

0 n ly applicable when governed by Figure 3.4.10-1, Curve A.

RCS heatup and cooldown rates are ~ 20°F in any one hour period.

SR 3.4.10.2 Verify RCS pressure and RCS temperature are to Once within 15 minutes the right of the criticality limit (Curve C) specified in prior to control rod Figure 3.4.10-3. withdrawal for the purpose of achieving criticality (continued)

SUSQUEHANNA - UNIT 2 TS I 3.4-26 Amendment tM, 24 7 I

RCS P/T Limits 3.4.10 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.10.6 ----------------------------NOTE----------------------------

Only required to be met in single loop operation when the idle recirculation loop is not isolated from the RPV, and:

a. THERMAL POWER :<=;; 27% RTP; or

b. The operating recirculation loop flow

<=;; 21,320 gpm.

Verify the difference between the reactor coolant Once within 15 minutes temperature in the recirculation loop not in prior to an increase in operation and the RPV coolant temperature is THERMAL POWER or

<=;; 50°F.

an increase in loop flow.

SR 3.4.10.7 ----------------------------N 0 TE----------------------------

0 nly required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange In accordance with the temperatures are:::: 70°F. Surveillance Frequency Control Proqram SR 3.4.10.8 ----------------------------NOTE----------------------------

Not required to be performed until 30 minutes after RCS temperature :<=;; 80°F in MODE 4.

Verify reactor vessel flange and head flange In accordance with the temperatures are:::: 70°F. Surveillance Frequency Control Proqram (continued)

SUSQUEHANNA - UNIT 2 TS I 3.4-28 Amendment 4-M, _?24, 24 7 I

RCS PIT Limits 3.4.10 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.4.10.9 ----------------------------NOTE----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature ::;; 100°F in MODE 4.

Verify reactor vessel flange and head flange In accordance with the temperatures are 2 70°F. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.4-29 Amendment ITT. 247 I

Reactor Steam Dome Pressure 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Reactor Steam Dome Pressure LCO 3.4.11 The reactor steam dome pressure shall be:::; 1050 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within dome pressure to within limit. limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify reactor steam dome pressure is In accordance with the

1050 psig. Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 2 TS/ 3.4-31 Amendment ~. 247 I

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, In accordance with the the piping is filled with water from the pump Surveillance Frequency discharge valve to the injection valve. Control Program SR 3.5.1.2 -----------------------------NOTE-----------------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal w~h reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection/spray subsystem In accordance with the manual, power operated, and automatic valve in Surveillance Frequency the flow path, that is not locked, sealed, or Control Program otherwise secured in position, and the HPCI flow controller are in the correct position.

SR 3.5.1.3 Verify ADS gas supply header pressure is In accordance with the

?". 135 psig. Surveillance Frequency Control ProQram SR 3.5.1.4 Verify at least one RHR System cross tie valve is In accordance with the closed and power is removed from the valve Surveillance Frequency operator. Control Program SR 3.5.1.5 Verify each 480 volt AC swing bus transfers In accordance with the automatically from the normal source to the Surveillance Frequency alternate source on loss of power. Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.5-4 Amendment :1-5-'r. 247 I

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 5. 1.9 ----------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure::; 165 psig, the HPCI In accordance with the pump can develop a flow rate?: 5000 gpm against Surveillance Frequency a system head corresponding to reactor pressure. Control Program SR 3.5.1.10 --------------------------------NOTE--------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem In accordance with the actuates on an actual or simulated automatic Surveillance Frequency initiation signal. Control Program SR 3.5.1.11 -------------------------------NOTE---------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated In accordance with the automatic initiation signal. Surveillance Frequency Control Program SR 3.5.1.12 Verify each ADS valve actuator strokes when In accordance with the manually actuated. Surveillance Frequency Control Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.5-6 Amendment 4-M, 24-+, 247 I

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.5.1.13 --------------------------NOTE--------------------------------

lnstrumentation response time is based on historical response time data.

Verify the ECCS RESPONSE TIME for each In accordance with the ECCS injection/spray subsystem is within limit. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.5-7 Amendment J..51, 247 I

ECCS-Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate action to restore Immediately associated Completion Time secondary containment to not met. OPERABLE status.

AND D.2 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

D.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required low pressure coolant In accordance with the injection (LPCI) subsystem, the suppression pool Surveillance Frequency water level is : : : 20 ft 0 inches. Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.5-9 Amendment 15-t; 247 I

ECCS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required core spray (CS) In accordance with the subsystem, the: Surveillance Frequency Control Program

a. Suppression pool water level is

~ 20 ft O inches; or

b. ---------------------------N 0 TE--------------------------

0 nly one required CS subsystem may take credit for this option during OPDRVs.

Condensate storage tank water level is ~ 49%

of capacity.

SR 3.5.2.3 Verify, for each required ECCS injection/spray In accordance with the subsystem, the piping is filled with water from the Surveillance Frequency pump discharge valve to the injection valve. Control Program SR 3. 5. 2. 4 ---------------------------NOTE-------------------------------

LPC I subsystems may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS injection/spray In accordance with the subsystem manual, power operated, and Surveillance Frequency automatic valve in the flow path, that is not locked, Control Program sealed, or otherwise secured in position, is in the correct position.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.5-10 Amendment j,..5-t, 247 I

EGGS-Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.5 Verify each required ECCS pump develops the In accordance with the specified flow rate against a system head lnservice Testing Program corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO.OF TOA REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF cs z6350 gpm 2 z 105 psig LPCI z 12,200 gpm 1 z 20 psig SR 3. 5. 2. 6 ----------------------------NO TE------------------------------

Vessel injection/spray may be excluded.

Verify each required ECCS injection/spray In accordance with the subsystem actuates on an actual or simulated Surveillance Frequency automatic initiation signal. Control Program SR 3. 5. 2. 7 ----------------------------NO TE------------------------------

1nstrumentation response time may be assumed to be the historical instrumentation response time.

Verify the ECCS RESPONSE TIME for each In accordance with the ECCS injection/spray subsystem is within limit. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.5-11 Amendment 1.54-; 24 7 I

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify the RCIC System piping is filled with water from In accordance with the pump discharge valve to the injection valve. the Surveillance Frequency Control Program SR 3.5.3.2 Verify each RCIC System manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, the Surveillance sealed, or otherwise secured in pos~ion, and the RCIC Frequency Control flow controller are in the correct position. Program SR 3. 5. 3. 3 ----------------------------------N 0 TE---------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure :::;; 1060 psig and In accordance

?: 920 psig, the RCIC pump can develop a flow rate with the lnservice

.: 600 gpm against a system head corresponding to Testing Program reactor pressure.

SR 3. 5. 3. 4 ------------------------------------NO TE-------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure :::;; 165 psig, the RCIC pump In accordance with can develop a flow rate ;: :.: 600 gpm against a system the Surveillance head corresponding to reactor pressure. Frequency Control ProQram (continued)

SUSQUEHANNA - UNIT 2 TS I 3.5-13 Amendment 1,S1. 247 I

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 5. 3. 5 ----------------------------------NOTE---------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.5-14 Amendment :J,31, 247 I

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.6.1.1.3 ------------------------------Note------------------------------

Satisfied by the performance of SR 3.6.1.1.2.

Verify that the total drywell-to-suppression In accordance with the chamber vacuum breaker leakage is less than or Surveillance Frequency 2

equal to .001605 ft and the leakage area for each Control Program set of vacuum breakers is less than or equal to 2

.000642 ft at an initial differential pressure of 24.3 psi.

SUSQUEHANNA - UNIT 2 TS/ 3.6-3 Amendment~ 247 I

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------------------NOTE-------------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria acceptable to SR 3.6.1.1.1.

Perform required primary containment air lock In accordance with the leakage rate testing in accordance with the Primary Primary Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary containment air In accordance with the lock can be opened at a time. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.6-7 Amendment JM. 247 I

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ---------------------------NOTES---------------------------

1. Only required to be met in MODES 1, 2, and 3.

2. Not required to be met when the 18 and 24 inch primary containment purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 and 24 inch primary containment In accordance with purge valve is closed. the Surveillance Frequency Control Program SR 3.6.1.3.2 ---------------------------N 0 TES---------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

In accordance with Verify each primary containment isolation manual the Surveillance valve and blind flange that is located outside Frequency Control primary containment and not locked, sealed, or Program otherwise secured and is required to be closed during accident conditions is closed.

(continued)

SUSQUEHANNA - UNIT 2 TS/ 3.6-12 Amendment jM, 247 J

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.3 --------------------------N 0 TES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual Prior to entering isolation valve and blind flange that is located MODE 2 or 3 from inside primary containment and not locked, MODE 4 if primary sealed, or otherwise secured and is required to containment was be closed during accident conditions is closed. de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity for each of the traversing incore In accordance with probe (TIP) shear isolation valve explosive the Surveillance charge. Frequency Control Proqram SR 3.6.1.3.5 Verify the isolation time of each power operated In accordance with and each automatic PCIV, except for MSIVs, is the lnservice within limits. Testing Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.6-13 Amendment J?'f'. 24 7 I

PC IVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.6 ----------------------------NOTE----------------------------

Only required to be met in MODES 1, 2 and 3.

Perform leakage rate testing for each primary In accordance with containment purge valve with resilient seals. the Surveillance Frequency Control Proqram SR 3.6.1.3.7 Verify the isolation time of each MSIV is In accordance with

~3 seconds and :::;; 5 seconds. the lnservice Testing Program SR 3.6.1.3.8 Verify each automatic PCIV actuates to the In accordance with isolation pos~ion on an actual or simulated the Surveillance isolation signal. Frequency Control Program SR 3.6.1.3.9 Verify a representative sample of reactor In accordance with instrumentation line EFCVs actuate to check flow the Surveillance on a simulated instrument line break. Frequency Control Program SR 3.6.1.3.10 Remove and test the explosive squib from each In accordance with shear isolation valve of the TIP System. the Surveillance Frequency Control Proi:iram (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.6-14 Amendment 4-68, ?00, 247 I

Containment Pressure 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Containment Pressure LCO 3.6.1.4 Containment pressure shall be -1.0 to 2.0 psig.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Containment pressure not A.1 Restore containment pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months within limit to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with the SR 3.6.1.4.1 Verify containment pressure is within limit.

Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.6-17 Amendment o/- 247 I

Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Drywell Air Temperature LCO 3.6.1.5 Drywell average air temperature shall be ::::; 135°F.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell average air 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within temperature to within limit.

limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Be in MODE4.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify drywell average air temperature is within In accordance with limit. the Surveillance Frequency Control Pro ram SUSQUEHANNA - UNIT 2 TS/ 3.6-18 Amendment ~247 I

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 ------------------------------NOTE----------------------------

Not required to be met for vacuum breakers that are open during Surveillances.

Verify each vacuum breaker is closed. In accordance with the Surveillance Frequency Control Program AND Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after discharge of steam to the suppression chamber from safety/relief valve SIR o eration.

(continued)

SUSQUEHANNA - UNIT 2 TS/ 3.6-20 Amendment~. 247 I

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.6.2 Perform a functional test of each required vacuum In accordance with breaker. the Surveillance Frequency Control Program Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after discharge of steam to the suppression chamber from S/RV operation Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months following an operation that causes any of the vacuum breakers to open SR 3.6.1.6.3 Verify the opening setpoint of each required In accordance with vacuum breaker is::::: 0.25 and::; .75 psid. the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.6-21 Amendment ~ 24 7 I

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Suppression pool average E.1 Depressurize the reactor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperature> 120°F. vessel to< 200 psig.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is In accordance with the within the applicable limits. Surveillance Frequency Control Program 5 minutes when performing testing that adds heat to the suppression pool SUSQUEHANNA - UNIT 2 TS/ 3.6-24 Amendment~* 247 I

Suppression Pool Water Level 3.6.2.2 3.6 CONTAl NMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be ~ 22 ft 0 inches and ~ 24 ft 0 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water level A.1 Restore suppression pool 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not within limits. water level to within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

AND B.2 Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is In accordance with the Surveillance within limits. Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.6-25 Amendment M, 247 I

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling In accordance with the subsystem manual, power operated, and Surveillance Frequency automatic valve in the flow path that is not locked, Control Program sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pump develops a flow rate In accordance with the

> 9750 gpm through the associated heat lnservice Testing Program exchanger while operating in the suppression pool cooling mode.

SUSQUEHANNA - UNIT 2 TS I 3.6-27 Amendment 1-31-, 247 I

RHR Suppression Pool Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR suppression pool spray In accordance with the subsystem manual, power operated, and Surveillance Frequency automatic valve in the flow path that is not locked, Control Program sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.4.2 Verify each suppression pool spray is In accordance with the unobstructed. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.6-29 Amendment 1-5.t;' 247 I

Drywell Air Flow System 3.6.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Operate each required drywell cooling fan at low In accordance with the speed for ;::: 15 minutes. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.6-33 Amendment :J..51, 247 I

Primary Containment Oxygen Concentration 3.6.3.3 3.6 CONTAINMENT SYSTEMS 3.6.3.3 Primary Containment Oxygen Concentration LCO 3.6.3.3 The primary containment oxygen concentration shall be < 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to ~ 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Primary containment oxygen A.1 Restore oxygen concentration 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months concentration not within limit. to within limit.

B. Required Action and B.1 Reduce THERMAL POWER to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion Time ~ 15% RTP.

not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.3.1 Verify primary containment oxygen concentration In accordance with the is within limits. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.6-34 Amendment t.31', 247 I

Secondary Containment 3.6.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Secondary containment C.1 -----------------NOTE----------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

C.2 Suspend CORE Immediately ALTERATIONS.

C.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is In accordance with the

~ 0.25 inch of vacuum water gauge. Surveillance Frequency Control Pro ram SR 3.6.4.1.2 Verify all required secondary containment In accordance with the removable walls and equipment hatches required Surveillance Frequency to be closed are closed and sealed. Control Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.6-36 Amendment 1~. 2P'1, m. 247 I

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

N 0 TE-----------------------------

S in gIe door access openings between required zones within the secondary containment boundary may be opened for entry and exit.

SR 3.6.4.1.3 Verify one secondary containment access door in In accordance with the each access opening is closed. Surveillance Frequency Control Program SR 3. 6 .4. 1.4 -----------------------------N 0 TE----------------------------- ---------------NOTE---------------

The maximum time allowed for secondary T est each configuration at containment draw down is dependent on the least one time every 60 secondary containment configuration. months.

Verify each standby gas treatment (SGT) In accordance with the subsystem will draw down the secondary Surveillance Frequency containment to ~ 0.25 inch of vacuum water gauge Control Program in less than or equal to the maximum time allowed for the secondary containment configuration that is OPERABLE.

SR 3.6.4.1.5 -----------------------------NOTE---------------------------- ---------------N 0 TE---------------

The maximum flow allowed for maintaining T est each configuration at secondary containment vacuum is dependent on least one time every 60 the secondary containment configuration. months.

Verify each SGT subsystem can maintain In accordance with the

~ 0.25 inch of vacuum water gauge in the Surveillance Frequency secondary containment for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow Control Program rate Jess than or equal to the maximum flow rate permitted for the secondary containment configuration that is OPERABLE.

SUSQUEHANNA - UNIT 2 TS I 3.6-37 Amendment 1,%1, 203, ~ 247 I

SC IVs 3.6.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 6. 4. 2. 1 ----------------------------NOTES----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each required secondary containment In accordance with the isolation manual valve and blind flange that is Surveillance Frequency required to be closed during accident conditions is Control Program closed.

SR 3.6.4.2.2 Verify the isolation time of each required In accordance with the automatic SCIV is within limits. Surveillance Frequency Control Program SR 3.6.4.2.3 Verify each required automatic SCIV actuates to In accordance with the the isolation position on an actual or simulated Surveillance Frequency actuation signal. Control Program SUSQUEHANNA - UNIT 2 TS/ 3.6-41 Amendment j,5-'( 247 I

SGT System 3.6.4.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two SGT subsystems F.1 ----------------NOTE----------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies in the secondary containment, during CORE Suspend movement of irradiated fuel Immediately ALTERATIONS, or during assemblies in secondary OPDRVs. containment.

F.2 Suspend CORE Immediately ALTERATIONS.

F.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT filter train for~ 10 continuous In accordance with the hours with heaters operating. Surveillance Frequency Control Proqram SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the VFTP with the Ventilation Filter Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual In accordance with the or simulated initiation signal. Surveillance Frequency Control Program SR 3.6.4.3.4 Verify each SGT filter cooling bypass and outside In accordance with the air damper opens and the fan starts on high Surveillance Frequency charcoal temperature. Control Program SUSQUEHANNA - UNIT 2 TS I 3.6-44 Amendment 1!i1, ~. 247 I

RHRSW System and UHS 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify the water level is greater than or equal to 678 feet In accordance with 1 inch above Mean Sea Level. the Surveillance Frequency Control Program SR 3.7.1.2 Verify the average water temperature of the UHS is: In accordance with the Surveillance Frequency Control Program

a. -------------------------------N 0 TE-----------------------------------

0 nly applicable with both units in MODE 1 or 2, or with either unit in MODE 3 for less than twelve (12) hours.

s 85°F; or

b. -------------------------------NOTE----------------------------------

0 nly applicable when either unit has been in MODE 3 for at least twelve (12) hours but not more than twenty-four (24) hours.

s 87°F; or

c. -------------------------------NOTE----------------------------------

Only applicable when either unit has been in MODE 3 for at least twenty-four (24) hours.

s 88°F.

SR 3.7.1.3 Verify each RHRSW manual, power operated, and In accordance with automatic valve in the flow path, that is not locked, sealed, the Surveillance or otherwise secured in position, is in the correct position or Frequency Control can be aligned to the correct position. Program In accordance with SR 3.7.1.4 Verify that valves HV-01222A and B (the spray array bypass the Surveillance valves) close upon receipt of a closing signal and open Frequency Control upon receipt of an opening signal.

Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.7-3 Amendment ..:1-§4, W, I tsO", 224,247

RHRSW System AND UHS 3.7.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY In accordance with SR 3.7.1.5 Verify that valves HV-01224A1 and 81 (the large spray the Surveillance array valves) close upon receipt of a closing signal and Frequency Control open upon receipt of an opening signal.

Program In accordance with SR 3.7.1.6 Verify that valves HV-01224A2 and 82 (the small spray the Surveillance array valves) close upon receipt of a closing signal and Frequency Control open upon receipt of an opening signal.

Program In accordance with SR 3.7.1.7 Verify that valves 012287A and 0122878 (the spray array the Surveillance bypass manual valves) are capable of being opened and Frequency Control closed.

Program SUSQUEHANNA - UNIT 2 TS/ 3.7-3a Amendment 400, ..224: 24 7 I

ESW System 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B or C not met. AND OR D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Both ESW subsystems inoperable for reasons other than Condition A and B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7. 2 .1 -----------------------------NOTE-----------------------------

lsolation of flow to individual components does not render ESW System inoperable.

Verify each ESW subsystem manual, power In accordance with the operated, and automatic valve in the flow paths Surveillance Frequency Control servicing safety related systems or components, Program that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.2.2 Verify each ESW subsystem actuates on an In accordance with the actual or simulated initiation signal. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.7-5 Amendment '!X247 I

CREOAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREOAS subsystems --------------------N 0 TE---------------------

inoperable during movement LCO 3.0.3 is not applicable.

of irradiated fuel assemblies --------------------------------------------------

in the secondary containment, during CORE F.1 Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

OR AND One or more CREOAS F.2 Suspend CORE Immediately subsystems inoperable due ALTERATIONS.

to an inoperable CRE boundary during movement of irradiated fuel AND assemblies in the secondary containment, during CORE F.3 Initiate action to suspend Immediately ALTERATIONS, or during OPDRVs.

OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7.3.1 Operate each CREOAS filter train for~ 10 In accordance with the continuous hours with the heaters operable. Surveillance Frequency Control Program SR 3.7.3.2 Perform required CREOAS filter testing in In accordance with the VFTP accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the SR 3.7.3.3 Verify each CREOAS subsystem actuates on an Surveillance Frequency Control actual or simulated initiation signal.

Program (continued)

SUSQUEHANA - UNIT 2 TS I 3.7-8 Amendment +:7-7, m. 247 I

Control Room Floor Cooling System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two control room floor --------------------N 0 TE---------------------

cooling subsystems LCO 3.0.3 is not applicable.

inoperable during movement of irradiated fuel assemblies in the secondary containment, during CORE E.1 Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies in OPDRVs. the secondary containment.

E.2 Suspend CORE Immediately ALTERATIONS.

E.3 Initiate actions to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7.4.1 Verify each control room floor cooling subsystem In accordance with the has the capability to remove the assumed heat Surveillance Frequency Control load. Program SUSQUEHANNA - UNIT 2 TS/ 3.7-12 Amendment :l.5-t; 247 I

Main Condenser Offgas 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7. 5. 1 ----------------------------N 0 TE------------------------------

Not required to be performed until 31 days after any main steam line is not isolated.

Verify the radioactivity rate of the specified noble In accordance with the gases is :-: : 330 mCi/second. Surveillance Frequency Control Program Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a

?: 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level SUSQUEHANNA - UNIT 2 TS/ 3.7-14 Amendment 1.5-t, 247 I

Main Turbine Bypass System 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each required main In accordance with the turbine bypass valve. Surveillance Frequency Control Program In accordance with the SR 3.7.6.2 Perform a system functional test. Surveillance Frequency Control Program SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM In accordance with the RESPONSE TIME is within limits. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.7-16 Amendment 1.51 485; w-3, 247 I

Spent Fuel Storage Pool Water Level 3.7.7

3. 7 PLANT SYSTEMS 3.7.7 Spent Fuel Storage Pool Water Level LCO 3.7.7 The spent fuel storage pool water level shall be~ 22 ft over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Spent fuel storage pool water A.1 ----------------N 0 TE-----------------

level not within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify the spent fuel storage pool water level is In accordance with the

~ 22 ft over the top of irradiated fuel assemblies Surveillance Frequency Control seated in the spent fuel storage pool racks. Program SUSQUEHANNA - UNIT 2 TS/3.7-17 Amendment~ 247 I

Main Turbine Pressure Regulation System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify that both Main Turbine Pressure Regulators In accordance with the are each capable of controlling main steam Surveillance Frequency pressure. Control Program In accordance with the SR 3.7.8.2 Perform a system functional test. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.7-19 Amendment 224;' 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS

NOTES---------------------------------------------------------

1. Four DGs are required and a DG is only considered OPERABLE when the DG is aligned to the Class 1 E distribution system. DG Surveillance Requirements have been modified to integrate the necessary testing to demonstrate the availability of DG E and ensure its OPERABILITY when substituted for any other DG. If the DG Surveillance Requirements, as modified by the associated Notes, are met and performed, DG E can be considered available and OPERABLE when substituted for any other DG after performance of SR 3.8.1.3 and SR 3.8.1.7.

2. SR 3.8.1.21 establishes Surveillance Requirements for the Unit 1 AC sources required to support Unit 2.

SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated In accordance with the power availability for each offsite circuit. Surveillance Frequency Control Program SR 3.8.1.2 Not Used.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-6 Amendment '\Zf, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.3 --------------------------NOTES----------------------------

1. DG loading may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.7.

5. DG E, when not aligned to the Class 1 E distribution system, may satisfy this SR using the test facility.

6. A single test will satisfy this Surveillance for both units if synchronization is to the 4.16 kV ESS bus for Unit 2 for one periodic test and synchronization is to the 4.16 kV ESS bus for Unit 1 for the next periodic test.

However, if it is not possible to perform the test on Unit 1 or test performance is not required per SR 3.8.2.1, then the test shall be performed synchronized to the 4.16 kV ESS bus for Unit 2.

Verify each DG is synchronized and loaded and In accordance with the operates for;::: 60 minutes at a load ;::: 3600 kW Surveillance Frequency Control and ::; 4000 kW. Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-7 Amendment 1.51, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each engine mounted day tank fuel oil In accordance with the level is ~ 420 gallons for DG A-D and ~ 425 Surveillance Frequency Control gallons for DG E. Program SR 3.8.1.5 Check for and remove accumulated water from In accordance with the each engine mounted day tank. Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system operates to In accordance with the automatically transfer fuel oil from the storage Surveillance Frequency Control tanks to each engine mounted tank. Program SR 3.8.1. 7 --------------------------NOTES---------------------------

1. All DG starts may be preceded by an engine prelube period.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts from standby condition In accordance with the and achieves, in ::; 10 seconds, voltage ~ 3793 V Surveillance Frequency Control and frequency~ 58.8, and after steady state Program conditions are reached, maintains voltage

~ 3793 V and ::; 4400 V and frequency ~ 58.8 Hz and::; 61.2 Hz.

SR 3.8.1.8 ----------------------------NOTE----------------------------

The automatic transfer of unit power suppty shall not be performed in MODE 1 or 2.

Verify automatic and manual transfer of unit In accordance with the power supply from the normal offsite circuit to the Surveillance Frequency Control alternate offsite circuit. Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.8-8 Amendment~. 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 8 .1 .9 ----------------------------NO TE----------------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG rejects a load greater than or In accordance with the equal to its associated single largest post-Surveillance Frequency Control accident load, and:

Program

a. Following load rejection, the frequency is

~ 64.5 Hz;

b. Within 4.5 seconds following load rejection, the voltage is ~ 3760 V and ~ 4560 V, and after steady state conditions are reached, maintains voltage ~ 3793 V and ~ 4400 V; and

c. Within 6 seconds following load rejection, the frequency is~ 58.8 Hz and~ 61.2 Hz.

SR 3.8.1.10 ---------------------------NOTE-----------------------------

A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG does not trip and voltage is In accordance with the maintained ~ 4560 V during and following a load Surveillance Frequency Control rejection of;:::-: 4000 kW. Program (continued)

SUSQUEHANNA - UNIT 2 TS/ 3.8-9 Amendment 1-51', 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.11 ----------------------------NOTES--------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2 or 3.

3. This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

In accordance with the Verify on an actual or simulated loss of offsite Surveillance Frequency Control power signal:

Program

a. De-energization of 4.16 kV ESS buses;

b. Load sheddng from 4.16 kV ESS buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in ~ 10 seconds,

2. energizes auto-connected shutdown loads through individual load timers,

3. maintains steady state voltage z 3793 V and ~ 4400 V,

4. maintains steady state frequency z 58.8 Hz and~ 61.2 Hz, and

5. supplies permanently connected loads for z 5 minutes.

(continued)

SUSQUEHANNA - UNIT 2 TS/ 3.8-10 Amendment j.5-t, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.12 ---------------------------NOTES---------------------------

1. All DG starts may be preceded by an engine prelube period.

2. DG E, when not aligned to the Class 1E distribution system, may satisfy this SR for both units by performance of SR 3.8.1.12.a, b and c using the test facility to simulate a 4.16 kV ESS bus. SR 3.8.1.12.d and e may be satisfied with either the normally aligned DG or DG E aligned to the Class 1E distribution system.

Verify, on an actual or simulated Emergency In accordance with the Core Cooling System (ECCS) initiation signal, Surveillance Frequency Control each DG auto-starts from standby condition and: Program

a. In :::; 1O seconds after auto-start achieves voltage ~ 3793 V, and after steady state conditions are reached, maintains voltage

~ 3793 V and :::; 4400 V;

b. In :::; 10 seconds after auto-start achieves frequency~ 58.8 Hz, and after steady state conditions are reached, maintains frequency

~ 58.8 Hz and:::; 61.2 Hz;

c. Operates for~ 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are energized or auto-connected through the individual load timers from the offsite power system.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-11 Amendment :J,.51', 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.13 ---------------------------NOTES---------------------------

1. A single test at the specified Frequency will satisfy this Surveillance for both units.

2. DG E when not aligned to the Class 1E distribution system may satisfy this SR by using a simulated ECCS initiation signal.

Verify each DG's automatic trips are bypassed on In accordance with the actual or simulated loss of voltage signal on the Surveillance Frequency Control 4.16 kV ESS bus concurrent with an actual or Program simulated ECCS initiation signal except:

a. Engine overspeed; and

b. Generator differential current; and

c. Low lube oil pressure.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-12 Amendment 1-Bi, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.14 ---------------------------NOTES---------------------------

1. Momentary transients outside the load ranges do not invalidate this test.

2. A single test at the specified Frequency will satisfy this Surveillance for both units.

3. DG E when not aligned to the Class 1E distribution system may satisfy this SR using the test facility.

In accordance with the Surveillance Frequency Control Verify each DG operates for z 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s: Program

a. For z 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded z 4400 kW and

~ 4 700 kW for DGs A through D and z 5000 kW and ~ 5500 kW for DG E; and

b. For the remaining hours of the test loaded z 3600 kW and ~ 4000 kW for DGs A through D and z 4500 kW and ~ 5000 kW for DG E.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-13 Amendment 1.51, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.15 ---------------------------NOTES---------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated ~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded

~ 3800 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

3. A single test at the specified Frequency will satisfy this Surveillance for both units.

Verify each DG starts and achieves, in In accordance with the

s; 10 seconds, voltage ~ 3793 V and frequency Surveillance Frequency

~ 58.8 and after steady state conditions are Control Program reached, maintains voltage~ 3793 V and

s; 4400 V and frequency~ 58.8 Hz and :s; 61.2 Hz.

(continued)

SUSQUEHANNA - UNIT 2 TS/ 3.8-14 Amendment '.1-&t, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.16 ---------------------------NOTE-----------------------------

This SR shall be performed for each DG on a rotational basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

In accordance with the Verify each DG: Surveillance Frequency Control Program

a. Synchronizes with offsite power sourre while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power sourre; and

c. Returns to ready-to-load operation.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-15 Amendment 1.31, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 ---------------------------NOTES---------------------------

This SR shall be performed for each DG on a rotational basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

Verify with a DG operating in test mode and In accordance with the connected to its bus, an actual or simulated Surveillance Frequency Control ECCS initiation signal overrides the test mode by: Program

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 ----------------------------NOTE----------------------------

Load timers associated with equipment that has automatic initiation capability disabled are not required to be OPERABLE.

In accordance with the Verify each sequenced load is within required Surveillance Frequency Control limits of the design interval.

Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-16 Amendment j,31, 24 7 J

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.8.1.19 ---------------------------NOTES---------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR shall be performed for each DG on a rotational test basis and for each 4.16 kV ESS bus at the specified FREQUENCY.

3. This Surveillance shall not be performed in MODE 1, 2 or 3.

Verify on an actual or simulated loss of offsite In accordance with the power signal in conjunction with an actual or Surveillance Frequency Control simulated ECCS initiation signal: Program

a. De-energization of 4.16 kV ESS buses;

b. Load sheddilg from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in ::::; 10 seconds,

2. energizes auto-connected emergency loads through individual load timers,

3. achieves steady state voltage ;::: 3793 V and::::; 4400 V,

4. achieves steady state frequency

58.8 Hz and

:::; 61.2 Hz, and

5. supplies permanently connected and auto-connected emergency loads for

5 minutes.

(continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-17 Amendment 15-t, 247 I

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8 .1.20 -------------------------------NOTES------------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This SR must be met, but does not have to be performed with DG E substituted for any DG.

Verify, when started simultaneously from standby In accordance with the condition, each DG achieves, in ~ 10 seconds, Surveillance Frequency Control voltage e: 3793 V and frequency e: 58.8 and after Program steady state conditions are reached, maintains voltage e: 3793 V and ~ 4400 V and frequency e: 58.8 Hz and~ 61.2 Hz.

SR 3.8.1.21 --------------------------NOTE------------------------------

When Unit 1 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 1 SR 3.8.2.1 is applicable.

For required Unit 1 AC sources, the following In accordance with SRs of Unit 1 Specification 3.8.1 are applicable: applicable SRs SR 3.8.1.1; SR 3.8.1.10; SR 3.8.1.3; SR 3.8.1.11; SR 3.8.1.4; SR 3.8.1.14; SR 3.8.1.5; SR 3.8.1.15; SR 3.8.1.6; SR 3.8.1.16; SR 3.8.1.7; SR 3.8.1.18; SR 3.8.1.9; SR 3.8.1.19; and SR 3.8.1.8 (when more than one Unit 1 offsite circuit is required)

SUSQUEHANNA - UNIT 2 TS I 3.8-18 Amendment j,51, 247 I

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains In accordance with the

47,570 gallons for DG A-D; Surveillance Frequency Control

60,480 gallons for DG E. Program SR 3.8.3.2 Verify lube oil SUfllJ level is visible in the sight In accordance with the glass. Surveillance Frequency Control Program SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance with the are tested in accordance with, and maintained Diesel Fuel Oil Testing within the limits of, the Diesel Fuel Oil Testing Program Program.

SR 3. 8. 3 .4 -----------------------------NO TE--------------------------

Not required to be met when DG is operating.

Verify each DG air start receiver pressure is In accordance with the

240 psig. Surveillance Frequency Control Program In accordance with the SR 3.8.3.5 Check for and remove accumulated water from Surveillance Frequency Control each fuel oil storage tank.

Program SUSQUEHANNA - UNIT 2 TS/ 3.8-25 Amendment 'WI'. 15?; 247 I

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or In accordance with the equal to the minimum established float voltage. Surveillance Frequency Control Program SR 3.8.4.2 Verify each required battery charger supplies its In accordance with the associated battery at the following rates for~ 4 Surveillance Frequency Control hours at greater than or equal to the minimum Program established float voltages:

a) ~ 100 amps for the 125V Battery b) ~ 300 amps for the 250V Battery c) ~ 200 amps for the125V Diesel Generator E Battery (continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-28 Amendment ta1, m, ~. 247 I

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3. 8. 4. 3 --------------------------NO TES--------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not be Performed in Mode 1, 2 or 3 except for the Diesel Generator E DC electrical power subsystem.

This Surveillance can be performed on the Diesel Generator E DC electrical power subsystem when the Diesel Generator E is not aligned to the Class 1 E distribution system. However, credit may be taken for unplanned e-.ents that satisfy this SR.

Verify battery capacity is adequate to supply, In accordance with the and maintain in OPERABLE status, the Surveillance Frequency Control required emergency loads for the design duty Program cycle when subjected to a battery service test.

SR 3. 8. 4 .4 ---------------------------N 0 TE-----------------------------

Wh en Unit 1 is in MODE 4 or 5, or moving irradiated fuel assemblies in the secondary containment, the Note to Unit 1 SR 3.8.5.1 is applicable.

For required Unit 1 DC electrical power In accordance with subsystems, the SRs for Unit 1 Specification applicable SRs 3.8.4 are applicable.

SUSQUEHANNA - UNIT 2 TS I 3.8-29 Amendment 1.31. 2-}2, m, 247 I

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1

NOTE----------------------------

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is ~ 2 amps. In accordance with the Surveillance Frequency Control Program SR 3.8.6.2 Verify each battery pilot cell voltage is ~ 2.07 V. In accordance with the Surveillance Frequency Control Proa ram SR 3.8.6.3 Verify each battery connected cell electrolyte In accordance with the level is greater than or equal to minimum Surveillance Frequency Control established design limits. Program SR 3.8.6.4 Verify each battery pilot cell temperature is In accordance with the greater than or equal to minimum established Surveillance Frequency Control design limits. Program (continued)

SUSQUEHANNA - UNIT 2 TS I 3.8-42 Amendment t5-1, 21-5, 24 7 I

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.5 Verify each battery connected cell voltage is In accordance with the

2.07V. Surveillance Frequency Control Program SR 3. 8. 6. 6 -------------------------NO TE------------------------------

Th is Surveillance shall not be Performed in Mode 1, 2, or 3. However, credit may be taken for unplanned e\tents that satisfy this SR.

Verify battery capacity is : : : 80% of the In accordance with the manufacturer's rating when subjected to a Surveillance Frequency Control performance discharge test or a modified Program performance discharge test.

12 months when battery shows degradation or has reached 85% of expected service life with capacity

< 100% of manufacturer's rating 24 months when battery has reached 85% of the expected service life with capacity 2: 100% of manufacturer's rating SUSQUEHANNA - UNIT 2 TS I 3.8-43 Amendment 15'1 , 2-1-5, 24 7 I

Distribution Systems-Operating 3.8.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and voltage or In accordance with the indicated power availability to required AC and Surveillance Frequency DC electrical power distribution subsystems. Control Program SUSQUEHANNA - UNIT 2 TS/ 3.8-47 Amendment :1.51,247 I

Distribution Systems-Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Diesel Generator E DC B.1 Verify that all ESW valves 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power distribution associated with Diesel subsystem inoperable, while Generator E are closed.

not aligned to the Class 1E distribution system.

C. Diesel Generator E DC C.1 Declare Diesel Generator E 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power distribution inoperable.

subsystem inoperable, while aligned to the Class 1E distribution system.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage or In accordance with the indicated power availability to required AC and Surveillance Frequency DC electrical power distribution subsystems. Control Program SUSQUEHANNA - UNIT 2 TS I 3.8-53 Amendment 1.31, 247 I

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each In accordance with the of the following required refueling equipment Surveillance Frequency interlock inputs: Control Program

a. All-rods-in,

b. Refuel platform position,

c. Refuel platform fuel grapple, fuel loaded,

d. Refuel platform frame mounted hoist, fuel loaded,

e. Refuel platform monorail mounted hoist, fuel loaded.

SUSQUEHANNA - UNIT 2 TS I 3.9-2 Amendment 1.5{', 247 I

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A Refuel position one-rod-out A.1 Suspend control rod withdrawal. Immediately interlock inoperable.

A.2 Initiate action to fully insert all Immediately insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in Refuel In accordance with the position. Surveillance Frequency Control Pro ram (continued)

SUSQUEHANNA - UNIT 2 TS I 3.9-3 Amendment ~247 j

Refuel Position One-Rod-Out Interlock 3.9.2 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3. 9 .2. 2 -----------------------------NO TE-----------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.9-4 Amendment ~247 I

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rods not A.1 Suspend loading fuel Immediately fully inserted. assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.9-5 Amendment 1.51, 247 I

Control Rod OPERABILITY-Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully insert Immediately control rods inoperable. inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 9. 5. 1 -----------------------------N 0 TE-----------------------------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one In accordance with the notch. Surveillance Frequency Control Program SR 3.9.5.2 Verify each withdrawn control rod scram In accordance with the accumulator pressure is~ 940 psig. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.9-8 Amendmentj..5-t;-247 I

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be ~ 22 ft above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new or irradiated fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A RPV water level not within A.1 Suspend movement of fuel Immediately limit. assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is ~ 22 ft above the top of In accordance with the the RPV flange. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.9-9 Amendment :J..81, 247 I

RHR-High Water Level 3.9.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is In accordance with the operating. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.9-12 Amendment~. 247 I

RHR-Low Water Level 3.9.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is In accordance with the operating. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/ 3.9-15 Amendment 15t. 247 I

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A (continued) A.3.1 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

OR A 3. 2 ------------NO TE-------------

Only applicable in MODES Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted in core cells In accordance with the containing one or more fuel assemblies. Surveillance Frequency Control Program SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.10-5 Amendment 1-81, 247 I

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS FREQUENCY SURVEILLANCE SR 3.10.3.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.3.2 ----------------------------NOTE------------------------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the control rod In accordance with the being withdrawn, in a five by five array centered Surveillance Frequency on the control rod being withdrawn, are disarmed. Control Program SR 3.10.3.3 Verify all control rods other than the control rod In accordance with the being withdrawn, are fully inserted. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.10-8 Amendment ;sf, 247 I

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more of the above B.1 Suspend withdrawal of Immediately requirements not met with the control rod and the affected control rod not removal of associated insertable. CRD.

AND B.2.1 Initiate action to fully Immediately insert all control rods.

B.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.4.2 ----------------------------NOTE------------------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the control rod In accordance with the being withdrawn, in a five by five array centered Surveillance Frequency on the control rod being withdrawn, are Control Program disarmed.

(continued)

SUSQUEHANNA - UNIT 2 TS/3.10-11 Amendment ta-t, 247 I

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.4.3 Verify all control rods, other than the control rod In accordance with the being withdrawn, are fully inserted. Surveillance Frequency Control Program SR 3.10.4.4 -----------------------------NOTE-----------------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is inserted. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS/3.10-12 Amendment :15-t: 247 I

Single CRD Removal - Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 Initiate action to fully Immediately insert all control rods.

A.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod In accordance with the withdrawn for the removal of the associated CRD, Surveillance Frequency are fully inserted. Control Program SR 3.10.5.2 Verify all control rods, other than the control rod In accordance with the withdrawn for the removal of the associated CRD, Surveillance Frequency in a five by five array centered on the control rod Control Program withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is inserted. In accordance with the Surveillance Frequency Control Program SR 3.10.5.4 PerformSR3.1.1.1. According to SR 3.1.1.1 (continued)

SUSQUEHANNA - UNIT 2 TS I 3.10-14 Amendment J..&t; 247 I

Single CRD Removal - Refueling 3.10.5 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE FREQUENCY SR 3.10.5.5 Verify no CORE ALTERATIONS are in progress. In accordance with the Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.10-15 Amendment J.at; 247 I

Multiple Control Rod Withdrawal - Refueling 3.10.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.1 Initiate action to fully Immediately insert all control rods in core cells containing one or more fuel assemblies.

A.3.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed from In accordance with the core cells associated with each control rod or Surveillance Frequency CRD removed. Control Program SR 3.10.6.2 Verify all other control rods in core cells containing In accordance with the one or more fuel assemblies are fully inserted. Surveillance Frequency Control ProQram SR 3.10.6.3 -----------------------------NOTE-----------------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in In accordance with the compliance with an approved reload sequence. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.10-17 Amendment 1-51, 247 I

SOM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.2 ----------------------------NOTE-----------------------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for LCO According to the applicable 3.3.2.1, Function 2 of Table 3.3.2.1-1. SRs SR 3.10.8.3 ----------------------------NOTE-----------------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in compliance During control rod movement with the approved control rod sequence for the SOM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in In accordance with the progress. Surveillance Frequency Control ProQram (continued)

SUSQUEHANNA - UNIT 2 TS I 3.10-22 Amendment 1-5-'r,247 I

SOM Test- Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not go to Each time the control rod is the withdravvn overtravel position. withdrawn to "full out" position Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure In accordance with the

.

940 psig. Surveillance Frequency Control Program SUSQUEHANNA - UNIT 2 TS I 3.10-23 Amendment~ 247 I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program (continued)

e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of OBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

5.5.15 Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

SUSQUEHANNA - UNIT 2 TS/ 5.0-18C Amendment 232, 247 I

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 266 AND 247 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-14 AND NPF-22 SUSQUEHANNA NUCLEAR, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-387 AND 50-388

1.0 INTRODUCTION

By application dated October 27, 2014 (Reference 1), as supplemented by letters dated July 2, 2015 (Reference 2); September 21, 2015 (Reference 3); November 11, 2015 (Reference 4);

and January 29, 2016 (Reference 18), Susquehanna Nuclear, LLC (Susquehanna or the licensee) submitted a license amendment request (LAR) proposing changes to the technical specifications (TSs) for the Susquehanna Steam Electric Station (SSES), Units 1 and 2.

The requested change is the adoption of U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force Traveler (TSTF)-425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b" (Reference 5). When implemented, TSTF-425 relocates most periodic frequencies of TS surveillances to a licensee controlled program, the Surveillance Frequency Control Program (SFCP), and provides requirements for the new program in the Administrative Controls section of the TSs. All surveillance frequencies can be relocated except:

Frequencies that reference other approved programs for the specific interval (such as the lnservice Testing Program or the Primary Containment Leakage Rate Testing Program);

Frequencies that are purely event-driven (e.g., "each time the control rod is withdrawn to the

'full out' position");

Frequencies that are event-driven but have a time component for performing the surveillance on a one-time basis once the event occurs (e.g., "within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after thermal power reaching<:: 95% RTP"); and

Frequencies that are related to specific conditions (e.g., battery degradation, age, and capacity) or conditions for the performance of a surveillance requirement (SR) (e.g., "drywell to suppression chamber differential pressure decrease").

A new program is added to the Administrative Controls of TS Section 5 as Specification 5.5.15.

The new program is called the Surveillance Frequency Control Program and describes the requirements for the program to control changes to the relocated surveillance frequencies. The TS Bases for each of the affected SRs are revised to state that the frequency is set in Enclosure 3

accordance with the SFCP. Some SR Bases do not contain a discussion of the frequency. In these cases, the Bases describing the current frequency were added to maintain consistency with the Bases for similar surveillances. These instances are noted in the markup along with the source of the text. The licensee's proposed changes to the Administrative Controls of the TSs to incorporate the SFCP include a specific reference to Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies" (Reference 6), as the basis for making any changes to the surveillance frequencies once they are relocated out of the TSs.

In a letter dated September 19, 2007 (Reference 7), the NRC staff approved NEI 04-10, Revision 1, as acceptable for referencing in licensing actions to the extent specified, and under the limitations delineated in NEI 04-10 and the safety evaluation, providing the basis for NRC acceptance of NEI 04-10.

The supplemental letters dated July 2, 2015; September 21, 2015; November 11, 2015; and January 29, 2016, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register (FR) on March 3, 2015 (80 FR 11479). The letter dated January 29, 2016, provided two revised marked-up pages to the SSES TSs to correct a typographical error that was provided with the marked-up TS pages included with the letter dated October 27, 2014.

This LAR was submitted by PPL Susquehanna, LLC; however, on June 1, 2015 (Reference 8),

the NRC staff issued an amendment changing the name on the SSES license from PPL Susquehanna, LLC to Susquehanna Nuclear, LLC. This amendment was issued subsequent to an order issued to SSES on April 10, 2015 (Reference 9), approving an indirect license transfer of the SSES license to Talen Energy Corporation.

2.0 REGULATORY EVALUATION

2.1 Applicable Commission Policy Statements In the "Final Policy Statement: Technical Specifications for Nuclear Power Plants," dated July 22, 1993 (58 FR 39132) the NRC addressed the use of Probabilistic Safety Analysis (PSA, currently referred to as Probabilistic Risk Assessment or PRA) in STS. In this 1993 publication, the NRC states:

The Commission believes that it would be inappropriate at this time to allow requirements which meet one or more of the first three criteria [of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36] 1 to be deleted from Technical Specifications based solely on PSA (Criterion 4). However, if the results of PSA indicate that Technical Specifications can be relaxed or removed, a deterministic review will be performed ....

1 This clarification is not part of the original policy statement.

The Commission Policy in this regard is consistent with its Policy Statement on "Safety Goals for the Operation of Nuclear Power Plants," 51 FR 30028, published on August 21, 1986. The Policy Statement on Safety Goals states in part, "* *

probabilistic results should also be reasonably balanced and supported through use of deterministic arguments. In this way, judgments can be made * *

about the degree of confidence to be given these [probabilistic] 2 estimates and assumptions. This is a key part of the process of determining the degree of regulatory conservatism that may be warranted for particular decisions.

This defense-in-depth approach is expected to continue to ensure the protection of public health and safety." ...

The Commission will continue to use PSA, consistent with its policy on Safety Goals, as a tool in evaluating specific line-item improvements to Technical Specifications, new requirements, and industry proposals for risk-based Technical Specification changes.

Approximately 2 years later, the NRC provided additional detail concerning the use of PRA in the "Final Policy Statement: Use of Probabilistic Risk Assessment in Nuclear Regulatory Activities," dated August 16, 1995 (60 FR 42622). In this publication, the NRC states:

The Commission believes that an overall policy on the use of PRA methods in nuclear regulatory activities should be established so that the many potential applications of PRA can be implemented in a consistent and predictable manner that would promote regulatory stability and efficiency. In addition, the Commission believes that the use of PRA technology in NRC regulatory activities should be increased to the extent supported by the state-of-the-art in PRA methods and data and in a manner that complements the NRC's deterministic approach ....

PRA addresses a broad spectrum of initiating events by assessing the event frequency. Mitigating system reliability is then assessed, including the potential for multiple and common cause failures. The treatment therefore goes beyond the single failure requirements in the deterministic approach. The probabilistic approach to regulation is, therefore, considered an extension and enhancement of traditional regulation by considering risk in a more coherent and complete manner....

Therefore, the Commission believes that an overall policy on the use of PRA in nuclear regulatory activities should be established so that the many potential applications of PRA can be implemented in a consistent and predictable manner that promotes regulatory stability and efficiency. This policy statement sets forth the Commission's intention to encourage the use of PRA and to expand the scope of PRA applications in all nuclear regulatory matters to the extent supported by the state-of-the-art in terms of methods and data ....

2 The Federc~I Register Notice 58 FR 39135 (Alteration in Original) explains the brackets.

Therefore, the Commission adopts the following policy statement regarding the expanded NRC use of PRA:

(1) The use of PRA technology should be increased in all regulatory matters to the extent supported by the state-of-the-art in PRA methods and data and in a manner that complements the NRC's deterministic approach and supports the NRC's traditional defense-in-depth philosophy.

(2) PRA and associated analyses (e.g., sensitivity studies, uncertainty analyses, and importance measures) should be used in regulatory matters, where practical within the bounds of the state-of-the-art, to reduce unnecessary conservatism associated with current regulatory requirements, regulatory guides, license commitments, and staff practices. Where appropriate, PRA should be used to support the proposal for additional regulatory requirements in accordance with 10 CFR 50.109 (Backfit Rule). Appropriate procedures for including PRA in the process for changing regulatory requirements should be developed and followed. It is, of course, understood that the intent of this policy is that existing rules and regulations shall be complied with unless these rules and regulations are revised.

(3) PRA evaluations in support of regulatory decisions should be as realistic as practicable and appropriate supporting data should be publicly available for review.

(4) The Commission's safety goals for nuclear power plants and subsidiary numerical objectives are to be used with appropriate consideration of uncertainties in making regulatory judgments on the need for proposing and backfitting new generic requirements on nuclear power plant licensees.

2.2 Applicable Regulations In 10 CFR 50.36, "Technical specifications," the NRC established its regulatory requirements related to the content of TS. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs);

(3) SRs; (4) design features; and (5) administrative controls. These categories will remain in the SSES TSs.

Section 50.36(c)(3) of 10 CFR states that, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." The FR notice published on July 6, 2009 (74 FR 31996),

which announced the availability of TSTF-425, Revision 3, states that the addition of the SFCP to the TSs provides the necessary administrative controls to require that surveillances frequencies relocated to the SFCP are conducted at a frequency to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met. The FR notice also states that changes to surveillance

frequencies in the SFCP are made using the methodology contained in NEI 04-10, Revision 1, including qualitative considerations, results of risk analyses, sensitivity studies and any bounding analyses, and recommended monitoring of structures, systems, and components (SSCs), and are required to be documented.

Existing regulatory requirements, such as 10 CFR 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants" (i.e., the Maintenance Rule), and 10 CFR 50, Appendix B, Criterion XVI, "Corrective Action," require licensee monitoring of surveillance test failures and implementing corrective actions to address such failures. Such failures can result in the licensee increasing the frequency at which a surveillance test is performed. In addition, the SFCP implementation guidance in NEI 04-10, Revision 1, provides for monitoring the performance of SSCs for which surveillance frequencies are decreased to assure reduced testing does not adversely impact the SSCs.

2.3 Applicable NRC Regulatory Guides and Review Plans Regulatory Guide (RG) 1.174, Revision 2, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis" (Reference 10), describes an acceptable risk-informed approach for assessing the nature and impact of proposed permanent licensing-basis changes by considering engineering issues and applying risk insights. This regulatory guide also provides risk acceptance guidelines for evaluating the results of such evaluations.

RG 1.177, Revision 1, "An Approach for Plant-Specific, Risk-Informed Decisionmaking:

Technical Specifications" (Reference 11 ), describes an acceptable risk-informed approach specifically for assessing proposed TS changes.

RG 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities" (Reference 12), describes an acceptable approach for determining whether the quality of the PRA, in total, or the parts that are used to support an application, is sufficient to provide confidence in the results such that the PRA can be used in regulatory decisionmaking for light water reactors.

3.0 TECHNICAL EVALUATION

The licensee's adoption of TSTF-425 for SSES provides for administrative relocation of applicable surveillance frequencies and provides for the addition of the SFCP to the Administrative Controls of TSs. TSTF-425 also requires the application of NEI 04-10 for any changes to surveillance frequencies within the SFCP. The licensee's application for the changes proposed in TSTF-425 included documentation regarding the PRA technical adequacy consistent with the guidance in RG 1.200. In accordance with NEI 04-10, PRA methods are used, in combination with plant performance data and other considerations, to identify and justify modifications to the surveillance frequencies of equipment at nuclear power plants. This is in accordance with guidance provided in RG 1.174 and RG 1.177 in support of changes to surveillance test intervals.

In Reference 1, the licensee provided revised TS Bases pages to be implemented with the associated TS changes. These pages were provided for information only and will be revised in accordance with the SSES TS Bases Control Program.

3.1 RG 1.177 Five Key Safety Principles RG 1.177 identifies five key safety principles required for risk-informed changes to TSs. Each of these principles is addressed by NEI 04-10.

3.1.1 The Proposed Change Meets Current Regulations Section 50.36(c)(3) of 10 CFR provides that TSs will include surveillances that are "requirements relating to test, calibration, or inspection to assure that necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." NEI 04-10 provides guidance for relocating the surveillance frequencies from the TSs to a licensee-controlled program by providing an NRG-approved methodology for control of the surveillance frequencies. The surveillances themselves would remain in the TSs, as required by 10 CFR 50.36(c)(3).

This change is consistent with other NRG-approved TS changes in which the surveillance frequencies are relocated to licensee-controlled documents, such as surveillances performed in accordance with the lnservice Testing Program or the Primary Containment Leakage Rate Testing Program. Thus, this proposed change meets the first key safety principle of RG 1.177 by complying with current regulations.

3.1.2 The Proposed Change is Consistent with the Defense-in-Depth Philosophy The defense-in-depth philosophy, the second key safety principle of RG 1.177, is maintained if:

A reasonable balance is preserved among prevention of core damage, prevention of containment failure, and consequence mitigation.

Over-reliance on programmatic activities to compensate for weaknesses in plant design is avoided.

System redundancy, independence, and diversity are preserved commensurate with the expected frequency, consequences of challenges to the system, and uncertainties (e.g., no risk outliers). Because the scope of the proposed methodology is limited to revision of surveillance frequencies, the redundancy, independence, and diversity of plant systems are not impacted.

Defenses against potential common cause failures are preserved, and the potential for the introduction of new common cause failure mechanisms is assessed.

Independence of barriers is not degraded.

Defenses against human errors are preserved.

The intent of the General Design Criteria in 10 CFR Part 50, Appendix A, is maintained.

TSTF-425 requires the application of NEI 04-1 O for any changes to surveillance frequencies within the SFCP. NEI 04-10 uses both the core damage frequency (CDF) and the large early release frequency (LERF) metrics to evaluate the impact of proposed changes to surveillance

frequencies. The guidance of RG 1.174 and RG 1.177 for changes to CDF and LERF is achieved by evaluation using a comprehensive risk analysis that assesses the impact of proposed changes, including contributions from human errors and common cause failures.

Defense-in-depth is also included in the methodology explicitly as a qualitative consideration outside of the risk analysis, as is the potential impact on detection of component degradation that could lead to an increased likelihood of common cause failures. Both the quantitative risk analysis and the qualitative considerations assure a reasonable balance of defense-in-depth is maintained to ensure protection of public health and safety, satisfying the second key safety principle of RG 1.177.

3.1.3 The Proposed Change Maintains Sufficient Safety Margins The engineering evaluation that will be conducted by the licensee under the SFCP when frequencies are revised will assess the impact of the proposed frequency change to assure that sufficient safety margins are maintained. The guidelines used for making that assessment will include ensuring the proposed surveillance test frequency change is not in conflict with approved industry codes and standards or adversely affects any assumptions or inputs to the safety analysis, or, if such inputs are affected, justification is provided to ensure sufficient safety margin will continue to exist.

The design, operation, testing methods, and acceptance criteria for SSCs specified in applicable codes and standards (or alternatives approved for use by the NRC) will continue to be met as described in the plant licensing basis (including the Updated Final Safety Analysis Report and Bases to TSs), since these are not affected by changes to the surveillance frequencies.

Similarly, there is no impact to safety analysis acceptance criteria as described in the plant licensing basis.

Thus, safety margins are maintained by the proposed methodology, and the third key safety principle of RG 1.177 is satisfied.

3.1.4 When Proposed Changes Result in an Increase in Core Damage Frequency or Risk, the Increases Should be Small and Consistent with the Intent of the Commission's Safety Goal Policy Statement RG 1.177 provides a framework for evaluating the risk impact of proposed changes to surveillance frequencies. This provides for the identification of the risk contribution from impacted surveillances, determination of the risk impact from the change to the proposed surveillance frequency, and performance of sensitivity and uncertainty evaluations. TSTF-425 provides for the application of NEI 04-10 in the SFCP. NEI 04-10 satisfies the intent of RG 1.177 guidance for evaluating the change in risk, and for assuring that such changes are small.

3.1.4.1 Quality of the PRA The quality of the SSES PRA must be commensurate with the safety significance of the proposed TS change and the role the PRA plays in justifying the change. That is, the higher

change in risk or the greater the uncertainty in that risk from the requested TS change, or both, the more rigor that must go into ensuring the quality of the PRA.

RG 1.200 provides regulatory guidance for assessing the technical adequacy of a PRA.

Revision 2 of this RG endorses (with comments and qualifications) the use of the American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) RA-Sa-2009, "Addenda to ASME RA-S-2008 Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications" (Reference 13), NEI 00-02, "PRA Peer Review Process Guidelines" (Reference 14) and NEI OS-04, "Process for Performing Follow-On PRA Peer Reviews Using the ASME PRA Standard" (Reference 1S). Revision 1 of this RG had endorsed the internal events PRA standard ASME RA-Sb-200S, "Addenda to ASME RA-S-2002 Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications" (Reference 16). For the internal events PRA, there are no significant technical differences in the standard requirements; however, the licensee should conform to the latest version of the ASME/ANS Standard as qualified and clarified to the latest version of RG 1.200.

The licensee has performed an assessment of the PRA models used to support the SFCP using the guidance of RG 1.200 to assure that the PRA models are capable of determining the change in risk due to changes to surveillance frequencies of SSCs using plant-specific data and models. Capability Category II of the standard is provided for in NEI 04-10 for the internal events PRA, and any identified deficiencies to those requirements are assessed further to determine any impacts of proposed decreases to surveillance frequencies, including the use of sensitivity studies where appropriate.

A full-scope PRA peer review of the SSES internal events and internal flood PRA was performed in October 2012 using the ASME/ANS RA-Sa-2009 PRA Standard as clarified and qualified by RG 1.200, Revision 2. There were 3S findings and observations (F&Os) from this peer review that were considered "not met (lower than CC II)."

The internal events PRA model addressed F&Os from the 2012 peer review assessment and provided a description of the resolutions and model revisions in Table 1 of the LAR. The NRC staff reviewed the F&Os provided in Attachment 1 of Reference 1. The NRC staff's evaluation of the F&Os for Supporting Requirements (SRs) that are unmet and Capability Category I are provided below.

F&O 4-4 for SR IE-AS: The F&O found that the Maintenance Rule plant systems were not all identified in the systematic evaluation to assess the possibility of an initiating event occurring due to a failure of the system. The licensee stated that the evaluation was completed but not properly documented. The licensee further stated that it placed the evaluation in Section 2.8 of the IE notebook. The NRC staff concludes that the licensee has properly dispositioned this F&O for the application because the licensee has updated its documentation to reflect the identification of the plant systems, and it does not impact the PRA model.

F&O 6-29 for SR IE-AS: The F&O observes that the licensee does not provide discussion on the effect of a loss of a single 13.8/4.16 kilovolt (kv) transformer in the initiating events workbook. The peer review team states that this is a suggestion because the discussions with the licensee indicated that the loss of a transformer would not result in a plant trip or a need for

shutdown. The licensee stated that it provided additional discussion on the loss of 13.8 and 4.16 kv transformers to Section 2.4.5 of the IE notebook to address this F&O. The NRC staff concludes that the licensee has dispositioned this F&O for the application because the licensee has updated its documentation to reflect the F&O, and it does not impact the PRA model.

F&O 1-12 for SR SC-A5: The F&O was created because the licensee did not perform an evaluation to determine if certain accident sequences should be extended beyond 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The licensee addressed this F&O by adding Section 2.1.17 to the success criteria notebook to outline the dominant considerations contributing to the 24-hour PRA mission time and the systems/equipment with less than a 24-hour mission time. The NRC staff requested that the licensee explain whether a safe and stable plant condition was achieved for the model accident sequences contributing to the 24-hour PRA mission time in request for additional information (RAI) 1, which was sent to the licensee via letter dated May 22, 2015 (Reference 17). In response to RAI 1 (Reference 2), the licensee stated, in part, that:

The Susquehanna PRA model is developed such that a safe and stable plant condition is achieved for modeled accident sequences with the assumed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months PRA mission time.

The licensee also clarified that:

[M]odeling of certain accident sequences is extended beyond 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when required to reach safe and stable plant conditions.

The NRC staff concludes that the licensee has adequately addressed mission times for application to the TSTF-425 program because it has accounted for safe and stable plant conditions for the 24-hour mission time and beyond.

F&O 1-24 for SR SC-A5: The F&O was created because the licensee allowed for a 25-hour mission time for the failure to run events for the Emergency Diesel Generators. The peer review team noted that the treatment was conservative and added a small increase in the failure probability. The licensee stated in Reference 2 that it reviewed the parameters and concluded that 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for failure to start and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for failure to run is conservative. The NRC staff concludes that the licensee's use of conservative values to represent failure to start and run is an adequate disposition of this F&O for the application.

F&O 1-18 for SR SY-C3: The F&O was created because the licensee identified four candidates as sources of uncertainty in the Summary Notebook Appendix D. The peer review team noted that the large number of modeling assumptions in the system notebooks should warrant a more thorough evaluation of plant-specific sources of uncertainty. The licensee reviewed all of the system notebook assumptions for applicability as potential sources of model uncertainty and added additional assumptions to Table D-2 in Appendix D of its Summary Notebook. The NRC staff concludes that the licensee's identification and documentation of the sources of uncertainty

is an adequate disposition for the F&O for the application because the licensee systematically addressed the sources of uncertainty.

F&O 7-4 for SR HR-82: The F&O was created because the peer review noted human reliability analysis (HRA) documentation indicating that due to staggered testing/maintenance practices, like components in different divisions are generally not susceptible to restoration error, and common mode errors are screened. The licensee explained in response to RAI 3 (Reference 2), based on its interpretation of SR HR-A3, which is referenced by HR-82, that the pre-initiator identification process would preclude the development of common mode misalignment events for like components in separate divisions. Therefore, it was not necessary to rely on staggered testing/maintenance principles for screening purposes. In response to RAI 8 (Reference 3), the licensee explained its interpretation of HR-A3 indicated that only single activities such as system misalignments, and not multiple activities that could result in common mode failures, were necessary to consider. The NRC staff did not agree that SR HR-A3 is limited to single activities since miscalibration potential exists if the same incorrect procedure is used, such as during testing and maintenance. In response to RAI 1O (Reference 4), the licensee stated that work practices, including procedures that simultaneously affect multiple equipment in either different trains of a redundant system or a diverse system are not screened.

Specifically, staggered testing is not used to screen common mode failures. Based on the detailed HRA pre-initiator process and the inclusion of staggered testing activities, the NRC staff finds that the F&O has been adequately addressed for the PRA model used for this application.

F&O 7-1 for SR HR-C3: The F&O was created because the licensee did not include an analysis of miscalibration for the component failure rate data. The licensee stated in the resolution for this F&O that adding this level of detail for single component miscalibration events is not warranted. In response to RAI 2 (Reference 2), the licensee explained further the PRA modeling of miscalibration for SR HR-C3. The licensee's pre-initiator methodology includes evaluating miscalibration as a failure mode of initiation of standby systems. Miscalibration is included for components/functions common mode events rather than at the level of a single component miscalibration event. The licensee determined that these single miscalibration events are very low contributors, and therefore, are not included in the PRA model. The NRC staff finds that the inclusion of miscalibration for common cause events is sufficient based on the licensee's evaluation that miscalibrations are not significant contributors for a single component failure mode.

F&Os 1-2 for SR HR-F1: The F&O was created because the licensee grouped the characteristics of several valves into a single human failure event (HFE) (i.e., MANOP_SPC_INJ_L-0). The peer review team cited the similarity in the degree of difficulty for opening valves and the performance shaping factors as examples of places where the licensee lacked justification for the groupings.

The licensee dispositioned this F&O by redefining the HFE into three new human error probabilities (HEP) and performing detailed evaluations for each. According to the ASME/ANS Standard, grouping HEP into a single HFE is acceptable for this program as long as the licensee provides justification for the similarities in failure modes or it can be conservatively bounded. The NRC staff concludes that the disposition is acceptable for the application because the licensee reevaluated and split the HFE.

F&O 1-3 for SR HR-F1: The F&O was created because the licensee did not include the evaluation of the time it takes for manual valve manipulation for HRA MAN-OP_SPC_INJ_L-0.

The licensee dispositioned this F&O by evaluating detailed timing manipulations and adding applicable references to the HRA documentation for the three new HEPs as mentioned in the discussion on F&O 1-2. The NRC staff concludes that the disposition is acceptable for the application because the licensee performed a detailed evaluation of the manual operation timing for three valves in the large diameter piping segments.

F&O 7-9 for SR HR-G6: The F&O was created because the licensee's comparison of events with similar HEP was incomplete. The licensee dispositioned this F&O by reviewing the documentation of the HEP and identifying and correcting any inconsistencies with the comparison of events with similar HEP. The NRC staff concludes that the disposition is acceptable for the application because the licensee performed the consistency check with a HEP ranking system relative to one another for correctness.

F&O 4-9 for SR DA-C6: The F&O was created because the licensee did not document its basis for plant failure data except to identify that its Mitigating Systems Performance Indices (MSPI) database and plant experience was the source. In light of this, the NRC staff concludes that the F&O will not significantly affect the program as this is a documentation concern.

F&O 4-12 for SRs DA-C12 and DA-C13: The F&O was created because the licensee did not evaluate the unavailability data, obtained from the MSPI for issues of "double counting." Also, the licensee did not consider the handling of unavailability hours that occurred online versus during an outage. The licensee stated that, "MSPI unavailability data is by its own program considered for reactor 'critical' hours. Unknown potential 'double counting' of MSPI data would be slightly conservative." The NRC staff concludes that the disposition is acceptable for the application because the licensee's consideration of MSPI data may result in conservative unavailability hours.

The licensee's internal flooding model was also included in the 2012 full scope peer review.

The internal flooding F&Os provided in the LAR show that the internal flooding model is incomplete and the F&Os have not been resolved. According to the LAR, the licensee is addressing these F&Os through a model update. The licensee indicated in the LAR that the internal flooding CDF and LERF contribution is expected to be small. The NRC staff finds that these F&Os can be addressed using the NEI 04-10 guidance on model incompleteness.

Based on the licensee's assessment using the applicable PRA standard and RG 1.200, the NRC staff concludes that the level of PRA quality, combined with the proposed evaluation and disposition of gaps, is sufficient to support the evaluation of changes proposed to surveillance frequencies within the SFCP and is consistent with Regulatory Position 2.3.1 of RG 1.177.

3.1.4.2 Scope of the PRA SSES has a full-power internal events and internal flood model that has received a peer review as discussed previously. The licensee is also required to evaluate each proposed change to a relocated surveillance frequency using the guidance contained in NEI 04-1 Oto determine its potential impact on risk (CDF and LERF) from internal events, fires, seismic, other external

events, and shutdown conditions. In cases where a PRA of sufficient scope or quantitative risk models is unavailable, the licensee uses bounding analyses or other conservative quantitative evaluations. A qualitative screening analysis may be used when the surveillance frequency impact on plant risk is shown to be negligible or zero.

The licensee will use these models to perform quantitative evaluations to support the development of changes to surveillance frequencies in the SFCP in accordance with NEI 04-10, Revision 1. In Attachment 1 to Reference 1, the licensee noted that the individual plant examination of external events (IPEEE) fire analysis "did yield a CDF, [but] the intent of the analysis was to identify the most risk significant fire areas in the plant using a screening process and by calculating conservative core damage frequencies for fire scenarios." The licensee also stated that its seismic analysis was also completed as part of the IPEEE. SSES used the Seismic Margins Assessment Electric Power Research Institute (EPRI) NP-6041-SLR1, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1),"

August 1991. In response to RAI 9 (Reference 3), the licensee confirmed that the fire risk and other external events will reflect current plant configuration and operating experience. The licensee also clarified the intent for internal fire risk, seismic events, and other external hazards for which there is no PRA model by stating that it will utilize a qualitative approach. This is an acceptable approach in accordance with NEI 04-10, Revision 1.

In Reference 1, the licensee explained that it does not currently have a shutdown PRA model.

However, the licensee explained that the guidance in NEI 04-10, Revision 1, will also be applied for shutdown events.

The licensee's evaluation methodology is sufficient to ensure the scope of the risk contribution of each surveillance frequency change is properly identified for evaluation and is consistent with Regulatory Position 2.3.2 of RG 1.177.

3.1.4.3 PRA Modeling The licensee's methodology includes the determination of whether the SSCs affected by a proposed change to a surveillance frequency are modeled in the PRA. Where the SSC is directly or implicitly modeled, a quantitative evaluation of the risk impact may be carried out.

The methodology adjusts the failure probability of the impacted SSCs, including any impacted common cause failure modes, based on the proposed change to the surveillance frequency.

Where the SSC is not modeled in the PRA, bounding analyses are performed to characterize the impact of the proposed change to the surveillance frequency. Potential impacts on the risk analyses due to screening criteria and truncation levels are addressed by the requirements for PRA technical adequacy consistent with guidance contained in RG 1.200 and by sensitivity studies identified in NEI 04-10.

The licensee's approach for the evaluations of the impact of selected testing strategy (i.e., staggered testing or sequential testing) is consistent with the guidance of NUREG/CR-6141 and NUREG/CR-5497, as discussed in NEI 04-10.

Thus, through the application of NEI 04-10, the SSES PRA modeling is sufficient to ensure an acceptable evaluation of risk for the proposed changes in surveillance frequency and is consistent with Regulatory Position 2.3.3 of RG 1.177.

3.1.4.4 Assumptions for Time-Related Failure Contributions The failure probabilities of SSCs modeled in PRAs may include a standby time-related contribution and a cyclic demand-related contribution. NEI 04-10 criteria adjust the time-related failure contribution of SSCs affected by the proposed change to surveillance frequency. This is consistent with RG 1.177, Section 2.3.3, which permits separation of the failure rate contributions into demand and standby for evaluation of SRs. If the available data do not support distinguishing between the time-related failures and demand failures, then the change to surveillance frequency is conservatively assumed to impact the total failure probability of the SSCs, including both standby and demand contributions. The SSC failure rate (per unit time) is assumed to be unaffected by the change in test frequency, such that the failure probability is assumed to increase linearly with time and will be confirmed by the required monitoring and feedback implemented after the change in surveillance frequency is implemented. The process requires consideration of qualitative sources of information with regard to potential impacts of test frequency on SSC performance, including industry and plant-specific operating experience, vendor recommendations, industry standards, and code-specified test intervals. Thus, the process is not reliant upon risk analyses as the sole basis for the proposed changes.

The potential benefits of reduced surveillance frequency, including reduced downtime, lesser potential for restoration errors, reduction of potential for test caused transients, and reduced test-caused wear of equipment, are identified qualitatively, but not quantitatively assessed.

NEI 04-10, provides for performance monitoring of SSCs whose surveillance frequencies have been revised as part of a feedback process to assure that the change in test frequency has not resulted in degradation of equipment performance and operational safety. The monitoring and feedback includes consideration of Maintenance Rule monitoring of equipment performance. In the event of SSC performance degradation, the surveillance frequency will be reassessed in accordance with the methodology, in addition to any corrective actions which may be required by the Maintenance Rule.

Thus, through the application of NEI 04-10, the licensee has employed reasonable assumptions with regard to extensions of surveillance test intervals, consistent with Regulatory Position 2.3.4 of RG 1.177.

3.1.4.5 Sensitivity and Uncertainty Analyses NEI 04-10 provides for sensitivity studies to assess the impact of uncertainties from key assumptions of the PRA, uncertainty in the failure probabilities of the affected SSCs, impact on the frequency of initiating events, and any identified deviations from Capability Category II of the PRA standard. Where the sensitivity analyses identify a potential impact on the proposed change, revised surveillance frequencies are considered, along with any qualitative considerations that may bear on the results of such sensitivity studies. Required monitoring and feedback of SSC performance once the revised surveillance frequencies are implemented will also be performed. Thus, through the application of NEI 04-10, the licensee has appropriately

considered the possible impact of PRA model uncertainty and sensitivity to key assumptions and model limitations, consistent with Regulatory Position 2.3.5 of RG 1.177.

3.1.4.6 Acceptance Guidelines The licensee will quantitatively evaluate the change in total risk (including internal and external events contributions) in terms of CDF and LERF for both the individual risk impact of a proposed change in surveillance frequency and the cumulative impact from all individual changes to surveillance frequencies using the guidance contained in NRC approved NEI 04-10 in accordance with the TS SFCP. Each individual change to surveillance frequency must show a risk impact below 1E-6 per year for change to CDF and below 1E-7 per year for change to LERF. These are consistent with the acceptance criteria of RG 1.174 for very small changes in risk. Where the RG 1.174 acceptance criteria are not met, the process either considers revised surveillance frequencies that are consistent with RG 1.174, or the process terminates without permitting the proposed changes. Where quantitative results are unavailable for comparison with the acceptance guidelines, appropriate qualitative analyses are required to demonstrate that the associated risk impact of a proposed change to surveillance frequency is negligible.

Otherwise, bounding quantitative analyses are required that demonstrate the risk impact is at least one order of magnitude lower than the RG 1.174 acceptance guidelines for very small changes in risk. In addition to assessing each individual SSC surveillance frequency change, the cumulative impact of all changes must result in a risk impact less than 1E-5 per year for change to CDF, and less than 1E-6 per year for change to LERF. The total CDF and total LERF must be reasonably shown to be less than 1E-4 per year and 1E-5 per year, respectively.

These are consistent with the acceptance criteria of RG 1.174, as referenced by RG 1.177 for changes to surveillance frequencies. The NRC staff further notes that the licensee includes a provision to exclude the contribution to cumulative risk from individual changes to surveillance frequencies associated with insignificant risk increases (less than 5E-8 CDF and 5E-9 LERF) once the baseline PRA models are updated to include the effects of the revised surveillance frequencies.

The quantitative acceptance guidance of RG 1.174 is supplemented by qualitative information to evaluate the proposed changes to surveillance frequencies, including industry and plant-specific operating experience, vendor recommendations, industry standards, the results of sensitivity studies, and SSC performance data and test history.

The final acceptability of the proposed change is based on all of these considerations and not solely on the PRA results. Post implementation performance monitoring and feedback are also required to assure continued reliability of the SSCs. The licensee's application of NEI 04-10 provides acceptable methods for evaluating the risk increase associated with proposed changes to surveillance frequencies, consistent with Regulatory Position 2.4 of RG 1.177. Therefore, the proposed methodology satisfies the fourth key safety principle of RG 1.177 by assuring any increase in risk is small, consistent with the intent of the Commission's Safety Goal Policy Statement.

3.1.5 The Impact of the Proposed Change Should be Monitored Using Performance Measurement Strategies The licensee's adoption of TSTF-425 requires application of NEI 04-10 in the SFCP. NEI 04-10 provides for performance monitoring of SSCs whose surveillance frequency has been revised as part of a feedback process to assure that the change in test frequency has not resulted in degradation of equipment performance and operational safety. The monitoring and feedback include consideration of Maintenance Rule monitoring of equipment performance. In the event of degradation of SSC performance, the surveillance frequency will be reassessed in accordance with the methodology, in addition to any corrective actions that may apply as part of the Maintenance Rule requirements. The performance monitoring and feedback specified in NEI 04-10 is sufficient to reasonably assure acceptable SSC performance and is consistent with Regulatory Position 3.2 of RG 1.177. Thus, the fifth key safety principle of RG 1.177 is satisfied.

3.2 Addition of Surveillance Frequency Control Program to Administrative Controls The licensee proposed including the SFCP and specific requirements into the SSES TSs, Section 5.5.15, as follows:

Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure that the associated Limiting Conditions for Operation are met.

a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.

b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI 04-10, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.

c. The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.

The proposed program is consistent with the model application of TSTF-425, and therefore, the NRC staff concludes that it is acceptable.

3.3 Deviations from TSTF-425 and Other Changes The licensee did not propose any deviations from TSTF-425 in Reference 1. However, Reference 2 did provide some changes to the licensee's request in Reference 1 based on

responses to RAls 6 and 7. Specifically, the licensee will not be moving the term "STAGGERED TEST BASIS," from TS Section 1.1, "Definitions," to the SFCP as was originally proposed because the term is retained in TS 5.5.14.d. Also, the licensee is no longer proposing to change the surveillance frequency of SR 3.6.1.1.2, based on its response to an RAI issued by the NRC staff in Reference 17.

3.4 Summary and Conclusions The NRC staff has reviewed the licensee's proposed relocation of specific surveillance frequencies to a licensee-controlled document and controlling changes to these surveillance frequencies in accordance with a new program, the SFCP, identified in the Administrative Controls of TSs. The NRC staff confirmed that this amendment does not relocate surveillance frequencies that reference other approved programs for the specific interval, are purely event-driven, are event-driven but have a time component for performing the surveillance on a one-time basis once the event occurs, or are related to specific conditions. The SFCP and TS Section 5.0, Subsection 5.5.15, references NEI 04-10, Revision 1, which provides a risk-informed methodology using plant-specific risk insights and performance data to revise surveillance frequencies within the SFCP. This methodology supports relocating surveillance frequencies from TSs to a licensee-controlled document, provided those frequencies are changed in accordance with NEI 04-10, Revision 1, which is specified in the Administrative Controls section of the TSs.

The proposed licensee adoption of TSTF-425, Revision 3, and risk-informed methodology of NRC-approved NEI 04-10, Revision 1, as referenced in the Administrative Controls section of TSs, satisfies the key principles of risk-informed decisionmaking applied to changes to TSs as delineated in RG 1.177 and RG 1.174, in that:

The proposed change meets current regulations;

The proposed change is consistent with defense-in-depth philosophy;

The proposed change maintains sufficient safety margins;

Increases in risk resulting from the proposed change are small and consistent with the Commission's Safety Goal Policy Statement; and

The impact of the proposed change is monitored with performance measurement strategies.

The regulation in 10 CFR 50.36(c) discusses the categories that will be included in TSs.

10 CFR 50.36(c)(3) specifically discusses the category of SRs and states, "Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met."

Based on the above evaluation, the NRC staff concludes that with the proposed relocation of surveillance frequencies to a licensee-controlled document and administratively controlled in accordance with the TS SFCP, the licensee continues to meet the requirements in 10 CFR 50.36(c)(3).

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the NRC staff notified the appropriate Pennsylvania State official of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or SRs. 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 NRC has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (80 FR 11479).

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

7.0 REFERENCES

1. Letter from Jon A. Franke to U.S. Nuclear Regulatory Commission, "Susquehanna Steam Electric Station Amendment Request for Adoption of Technical Specification Task Force Traveler (TSTF)-425, Revision 3, 'Relocate Surveillance Frequencies to Licensee Control -

RITSTF Initiative 5b,' "October 27, 2014 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML14317A052).

2. Letter from Jon A. Franke to U.S. Nuclear Regulatory Commission, "Susquehanna Steam Electric Station Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-425," July 2, 2015 (ADAMS Accession No. ML15183A248).

3. Letter from Jon A. Franke to U.S. Nuclear Regulatory Commission, "Susquehanna Steam Electric Station Response to Request for Additional Information Technical Specification Changes to Adopt Traveler TSTF-425," September 21, 2015 (ADAMS Accession No. ML15265A347).

4. Letter from Jon A. Franke to U.S. Nuclear Regulatory Commission, "Susquehanna Steam Electric Station Response to Request for Additional Information on Technical Specification Changes to Adopt Traveler TSTF-42S," November 11, 201 S (ADAMS Accession No. ML 1S31SA04S).

S. TSTF-42S, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative Sb," March 18, 2009 (ADAMS Package Accession No. ML0908S0642).

6. NEI 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative Sb, Risk-Informed Method for Control of Surveillance Frequencies," April 2007 (ADAMS Accession No. ML0713604S6).

7. Final Safety Evaluation for NEI Topical Report 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative Sb, Risk-Informed Method for Control of Surveillance Frequencies,"

September 19, 2007 (ADAMS Accession No. ML072S70267).

8. NRC Letter, "Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Conforming Amendment Re: Indirect Transfer of Renewed Facility Operating Licenses to Susquehanna Nuclear, LLC," June 1, 201 S (ADAMS Accession No. ML 1SOS4A066).

9. NRC, "Order Approving Transfer of Licenses and Conforming Amendments," related to the Susquehanna Steam Electric Station, Units 1 and 2, April 10, 201 S (ADAMS Accession No. ML 1SOS8A073).

10. Regulatory Guide 1.174, Revision 2, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," May 2011 (ADAMS Accession No. ML100910006).

11. Regulatory Guide 1.177, Revision 1, "An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications," May 2011 (ADAMS Accession No. ML100910008).

12. Regulatory Guide 1.200, Revision 2, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," March 2009 (ADAMS Accession No. ML090410014).

13. ASME/ANS PRA Standard ASME/ANS RA-Sa-2009, Addenda to ASME RA-S-2008, "Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications."

14. NEI 00-02, Revision 1, "Probabilistic Risk Assessment (PRA) Peer Review Process Guidance," May 2006 (ADAMS Accession No. ML061S10614).

1S. NEI OS-04, "Process for Performing Follow-On PRA Peer Reviews Using the ASME PRA Standard," Revision 0, August 2006.

16. ASME PRA Standard ASME RA-Sb-2005, Addenda to ASME RA-S-2002, "Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications."

17. NRC Letter, "Susquehanna Steam Electric Station, Units 1 and 2 - Request for Additional Information Re: License Amendment Request to Adopt Technical Specification Task Force Traveler (TSTF)-425," May 22, 2015 (ADAMS Accession No. ML15103A396).

18. Letter from Jon A. Franke to U.S. Nuclear Regulatory Commission, "Susquehanna Steam Electric Station Supplemental information on Technical Specification Changes to Adopt Traveler TSTF-425," January 29, 2016 (ADAMS Accession No. ML16032A324).

Principal Contributor: J. Evans, NRR Date: May 20, 2016

Package: ML16141A098 Amendment: ML16005A234 Non-Concurrence: ML16141A025 *b e-mail OFFICE DORL/LPLl-2/PM DORL/LPLl-2/LA DRA/APLA/BC DSS/STSB/BC (A)* DE/EE EB DE/EE EB NAME JWhited LRonewicz SRosenberg A Klein TMartinez-Navedo SS om GMatharu non-concur) (non-concur) (non-concur)

DATE 02/18/2016 02/12/2016 05/20/2016 05/10/2016 04/13/2016 04/13/2016 04/13/2016 OFFICE DE/EE EB DE/EEEB DE/EEEB/BC OGC (NLO) DORL/LPLl-2/BC (A) DORL/LPLl-2/PM SRay RMathew JZimmerman Jlindell DBroaddus NAME JWhited non-concur non-concur non-concur wl comments AHon for DATE 04/13/2016 04/13/2016 04/26/2016 05/18/2016 05/20/2016 05/20/2016

v t e Letter Sequence Approval
CAC:MF5151, (Approved, Closed) CAC:MF5152, (Approved, Closed)
Initiation Acceptance... Supplement Administration Meeting Questions 15 October 2015 Answers Results Approval Other: ML16141A025
MONTHYEAR2016-01-29 [Table View]

ML16005A234

Text

SUBJECT:

Dear Mr. Franke:

Enclosures:

Attachment:

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

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