Text

Revised FOL & TS Pages
	ML081000429
Person / Time
Site:	Susquehanna
Issue date:	05/05/2008
From:	Bhalchandra Vaidya; NRC/NRR/ADRO/DORL/LPLI-1
To:	Mckinney B; Susquehanna
	vaidya B, NRR/Dorl/lpl1-1, 415-3308
References
	TAC MD3309, TAC MD3310
	Download: ML081000429 (6)
	v • d • e

(a) The following requirements are placed on operation of the PPL Susquehanna, LLC (PPL) facility above the licensed thermal power (CLTP) level of 3489 megawatts thermal (MWt):

1.

PPL shall obtain at each 3.5% power ascension step up to 107% of 3489 MWt, dryer strain gauge data and compare it to the acceptance criteria during power ascension above 3489 MWt. PPL shall obtain at each 3.5% power ascension step above 107% of 3489 MWt, main steam line strain gauge data and compare it to the limit curve for the dryer strains during power ascension.

2.

PPL shall monitor the main steam line (MSL) strain gauges during power ascension testing above 3489 MWt for increasing pressure fluctuations in the steam lines.

3.

PPL shall hold the facility at each 3.5% ascension step to collect data from License Condition 2.C.(36)(a) and conduct plant inspections and walk-downs, and evaluate steam dryer performance based on the data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after the NRC project manager confirms receipt of the transmission.

4.

If any steam dryer strains at each 3.5% power ascension step up to 107% of 3489 MWt or frequency peak from the MSL strain gauge data exceeds the level 1 limit curve for the MSL strains above 107% of 3489 MWt, PPL shall return the facility to a power level at which the acceptance criteria is not exceeded. PPL shall resolve the discrepancy, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.

5.

In addition to evaluating the dryer instrumentation data and MSL strain gauge data, PPL shall monitor reactor pressure vessel water level instrumentation and MSL piping accelerometers during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, PPL shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.

6.

Following CPPU start-up testing, PPL shall resolve any discrepancies in the steam dryer analysis and provide that resolution to the NRC staff by facsimile or electronic transmission to the NRC project manager. If the discrepancies are not resolved within 90 days of identification, PPL shall return the facility to a power level at which the discrepancy does not exist.

Amendment No. 5, 15, 178, 188, 246 Correction Letter Dated May 5, 2008 program requirements and the provisions of the power ascension test program prior to continued operation of either SSES Unit above 3733 MWt.

(38)

Neutronic Methods (a) An OPRM amplitude setpoint penalty will be applied to account for a reduction in thermal neutrons around the LPRM detectors caused by transients that increase voiding. This penalty will reduce the OPRM scram setpoint according to the methodology described in Response No. 3 of PPL letter, PLA-6306, dated November 30, 2007. This penalty will be applied until NRC evaluation determines that a penalty to account for this phenomenon is not warranted.

(b) For SSES SLMCPR, a conservatively adjusted pin power distribution uncertainty and bundle power correlation coefficient will be applied as stated in Response No. 4 of PPL letter, PLA-6306, dated November 30, 2007, when performing the analyses in accordance with ANF-524(P)(A), "Critical Power Methodology for Boiling Water Reactors,"

using the uncertainty parameters associated with EMF-2158(P)(A)

"Siemens Power Corporations Methodology for Boiling Water Reactors:

Evaluation and Validation of CASMO-4/MICROBURN-B2 "

(39)

Containment Operability for EPU PPL shall ensure that the CPPU containment analysis is consistent with the SSES 1 and 2 operating and emergency procedures. Prior to operation above CLTP, for each respective unit, PPL shall notify the NRC project manager that all appropriate actions have been completed.

(40)

Primary Containment Leakage Rate Testing Program Those primary containment local leak rate program tests (Type B - leakage-boundary and Type C - containment isolation valves) as modified by approved exemptions, required by 10 CFR Part 50, Appendix J, Option B and Technical Specification 5.5.12, are not required to be performed at the CPPU peak calculated containment internal pressure of 48.6 psig (Amendment No. 246 to this Operating License) until their next required performance.

D.

The operating licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Susquehanna Steam Electric Station Physical Security Plan, with revisions submitted through September 24, 1987; Susquehanna Steam Electric Station Guard Training and Qualification Plan, with revisions submitted through May 28, 1985; and Amendment No. 13, 81, 178, 188, 246, 247

Amendment No. 246 corrected by letter dated May 5, 2008

PPL Rev. 3 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SUSQUEHANNA - UNIT 1 3.3-4 Amendment 178 SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.

7 days SR 3.3.1.1.6 Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap.

Prior to fully 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.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 MWD/MT average core exposure SR 3.3.1.1.9

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

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

Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.1.1.10 Perform CHANNEL CALIBRATION.

92 days (continued)

, 246 Correction Letter Dated May 5, 2008 Amendment 162, 224 Correction Letter Dated May 5, 2008 transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after the NRC project manager confirms receipt of transmission.

4.

If any frequency peak from the MSL strain gauge data exceeds the level 1 limit curve for dryer strains above 3489 MWt, PPL shall return the facility to a power level at which the acceptance criteria is not exceeded. PPL shall resolve the discrepancy, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.

5.

In addition to evaluating the dryer strain and MSL strain gauge data, PPL shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers during power ascension above 3489 MWt. If resonance frequencies are identified as increasing above nominal levels in proportion to instrumentation data, PPL shall stop power ascension, document the continued structural integrity of the steam dryer, and provide that documentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.

6.

Following CPPU start-up testing, PPL shall resolve the discrepancies in the steam dryer analysis and provide that resolution to the NRC staff by facsimile or electronic transmission to the NRC project manager. If the discrepancies are not resolved within 90 days of identification, PPL shall return the facility to a power level at which the discrepancy does not exist.

(b)

PPL shall implement the following actions:

1.

PPL shall provide to NRC the as-built dryer stress analysis and load limit curves 45 days prior to operation above 3489 MWt.

2.

After the dryer stress analysis is benchmarked to the Unit 1 startup test data (Unit 1 data taken up to 107 % of 3489 MWt), the benchmarked PATP and MSL limit curves shall be provided to the NRC 90 days prior to operation above 107% of 3489 MWt.

3.

In the event that acoustic signals are identified that challenge the limit curves during power ascension above 3489 MWt, PPL shall evaluate dryer loads and re-establish the acceptance criteria based on the new data, and shall perform an assessment of ACM uncertainty at the acoustic signal frequency.

4.

After reaching full CPPU, PPL shall obtain measurements from the MSL strain gauges and establish the steam dryer flow-induced vibration load fatigue margin for the facility, update the dryer stress report, if required, and re-establish the limit curve with the updated ACM load definition and revised instrument uncertainty, which will be provided to the NRC staff.

(23) Containment Operability for EPU PPL shall ensure that the CPPU containment analysis is consistent with the SSES 1 and 2 operating and emergency procedures. Prior to operation above CLTP, for each respective unit, PPL shall notify the NRC project manager that all appropriate actions have been completed.

(24) Primary Containment Leakage Rate Testing Program Those primary containment local leak rate program tests (Type B -

leakage-boundary and Type C - containment isolation valves) as modified by approved exemptions, required by 10 CFR Part 50, Appendix J, Option B and Technical Specification 5.5.12, are not required to be performed at the CPPU peak calculated containment internal pressure of 48.6 psig (Amendment No. 224 to this Operating License) until their next required performance.

2. D. The operating licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: Susquehanna Steam Electric Station Physical Security Plan, with revisions submitted through September 24, 1987; Susquehanna Steam Electric Station Guard Training and Qualification Plan, with revisions submitted through May 28, 1985; and Susquehanna Steam Electric Station Safeguards Contingency Plan, with revisions submitted through September 24, 1987.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedules set forth therein.

E.

Deleted Amendment No. 162, 224, 226

Amendment No. 224 corrected by letter dated May 5, 2008

PPL Rev. 2 RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SUSQUEHANNA - UNIT 2 3.3-4 Amendment 151 SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.