ML16141A048
| ML16141A048 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/19/2016 |
| From: | Waldrep B Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CAC MF6413, CAC MF6414, CAC MF6415, CAC MF6416, CAC MF6417, CAC MF6418, CAC MF6419, CAC MF6420, CAC MF6421, CAC MF6422, TAC MF6583 | |
| Download: ML16141A048 (34) | |
Text
Benjamin C. Waldrep Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919.362.2502 10 CFR 50.90 May 19, 2016 Serial: HNP-16-040 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 Renewed License No. NPF-63
Subject:
Supplement to the Harris Nuclear Plant License Amendment Request to Revise Technical Specifications by Relocating Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TAC MF6583)
References:
- 1. Duke Energy letter, Harris Nuclear Plant, Unit 1, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, dated August 18, 2015 (ML15236A254).
- 2. Duke Energy letter, Harris Nuclear Plant, Unit 1, Supplement to Harris Nuclear Plant Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program, dated September 29, 2015 (ML15272A443)
- 3. Nuclear Regulatory Commission letter, Brunswick Steam Electric Plant, Unit Nos. 1 and 2; Shearon Harris Nuclear Power Plant, Unit 1; Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; and Oconee Nuclear Station, Units 1, 2, and 3:
Issuance of Amendments Regarding Adoption of TSTF-523 (CAC Nos. MF6413 Through MF6422), dated April 29, 2016 (ML16085A113)
Ladies and Gentlemen:
By letter dated August 18, 2015 (Reference 1), as supplemented by letter dated September 29, 2015 (Reference 2), Duke Energy Progress, Inc. (Duke Energy), submitted a License Amendment Request (LAR) proposing changes to the Technical Specifications (TS) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed amendment would modify HNP TS by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5B, Risk-Informed Method for Control of Surveillance Frequencies (ML071360456).
Since the submittal of References 1 and 2, the Nuclear Regulatory Commission (NRC) has issued a license amendment by letter dated April 29, 2016 (Reference 3), that includes additional Surveillance Requirements (SR) that fall within the scope of this LAR. As such, their inclusion in this LAR is requested. This supplement to the original submittal in Reference 1 is an administrative change in the marked-up pages.
U.S. Nuclear Regulatory Commission Serial HNP-16-040 Page 2of2 to this letter provides the Reference 3 HNP TS pages showing the proposed changes. Attachment 2 provides the update to the Reference 1 Enclosure 6 cross-reference between Technical Specification Task Force (TSTF) Standard Technical Specifications (STS)
Change TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative Sb," Revision 3 (ML090850642), and the HNP TS containing surveillance frequencies proposed for relocation. Revisions are indicated by a bar in the left hand margin of the attachment.
This additional information does not change the No Significant Hazards Determination provided in Reference 1. No Regulatory Commitments are contained in this letter.
In accordance with 10 CFR 50.91(b), HNP is providing the state of North Carolina with a copy of this supplemental correspondence.
Should you have any questions regarding this submittal, please contact John Caves, Regulatory Affairs Manager, at 919-362-2406.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on May/q, 2016.
Sincerely, Benjamin C. Waldrep Vice President, Shearon Harris Nuclear Power Plant Attachments:
- 1. Additional Proposed Technical Specification Changes
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, Ill, Section Chief, N.C. DHSR Ms. M. Barillas, NRC Project Manager, HNP Ms. Catherine Haney, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Page 2 of 2 Serial HNP-16-040 to this letter provides the Reference 3 HNP TS pages showing the proposed changes. Attachment 2 provides the update to the Reference 1 Enclosure 6 cross-reference between Technical Specification Task Force (TSTF) Standard Technical Specifications (STS)
Change TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, Revision 3 (ML090850642), and the HNP TS containing surveillance frequencies proposed for relocation. Revisions are indicated by a bar in the left hand margin of the attachment.
This additional information does not change the No Significant Hazards Determination provided in Reference 1. No Regulatory Commitments are contained in this letter.
In accordance with 10 CFR 50.91(b), HNP is providing the state of North Carolina with a copy of this supplemental correspondence.
Should you have any questions regarding this submittal, please contact John Caves, Regulatory Affairs Manager, at 919-362-2406.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on May, 2016.
Sincerely, Benjamin C. Waldrep Vice President, Shearon Harris Nuclear Power Plant Attachments:
- 1. Additional Proposed Technical Specification Changes
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief, N.C. DHSR Ms. M. Barillas, NRC Project Manager, HNP Ms. Catherine Haney, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial HNP-16-040 SERIAL HNP-16-040 ATTACHMENT 1 ADDITIONAL PROPOSED TECHNICAL SPECIFICATION CHANGES SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 (8 PAGES)
at the frequency specified in the Surveillance Frequency Control Program
at the frequency specified in the Surveillance Frequency Control Program
at the frequency specified in the Surveillance Frequency Control Program
At the frequency specified in the Surveillance Frequency Control Program
At the frequency specified in the Surveillance Frequency Control Program
at the frequency specified in the Surveillance Frequency Control Program
at the frequency specified in the Surveillance Frequency Control Program
U.S. Nuclear Regulatory Commission Serial HNP-16-040 SERIAL HNP-16-040 ATTACHMENT 2 UPDATED CROSS-REFERENCE BETWEEN HNP TECHNICAL SPECIFICATIONS AND TSTF-425, REVISION 3 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63 (23 PAGES)
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 2 of 23 Cross-Reference between Shearon Harris Nuclear Power Plant, Unit 1 (HNP) Technical Specifications and TSTF-425, Revision 3 (NUREG-1431 Mark-up)
For HNP plant-specific surveillances that do not have a corresponding surveillance included in the NUREG-1431 mark-ups provided in TSTF-425, Duke Energy evaluated these surveillance frequencies against the four exclusion criteria delineated in TSTF-425, Revision 3. The four criteria which exclude surveillance frequencies from being relocated are:
Frequencies that reference other approved programs for the specific interval (such as the Inservice 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after thermal power reaching 95%RTP);
Frequencies that are related to specific conditions (e.g. battery degradation, age and capacity) or conditions for the performance of a surveillance requirement (e.g., drywell to suppression chamber differential pressure decrease).
HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.1.1.1 SHUTDOWN MARGIN - MODES 1 and 2 4.1.1.1.1.b Verify control bank withdrawal within limits NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.1.1.1.2 Verify measured core reactivity within predicted value 3.1.2.1 3.1.1.2 SHUTDOWN MARGIN - MODES 3, 4, and 5 4.1.1.2.b Verify Shutdown Margin NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 3 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.1.2.1 Boration Systems - Flow Path - Shutdown 4.1.2.1.b Verify boric acid flow path valve positions NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.1.2.2 Boration Systems - Flow Path - Operating 4.1.2.2.b Verify boric acid flow path valve positions NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.1.2.2.c Verify boric acid flow path automatic valve actuation 4.1.2.2.d Verify boric acid flow path flow rate 3.1.2.3 Boration Systems - Charging Pump - Shutdown 4.1.2.3.2 Demonstrate all but one charging/safety injection pumps inoperable 3.4.12.1 3.4.12.2 3.1.2.5 Boration Systems - Borated Water Source - Shutdown 4.1.2.5.a.1 Verify borated water source boron concentration Requirements for Modes 5 and 6 were not specified in NUREG-1431, however similar changes for Modes 1 through 4 were done in TSTF-425 SR 3.5.4.2 and 3.5.4.3. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.1.2.5.a.2 Verify borated water source volume 4.1.2.5.a.3 Verify boric acid tank solution temperature NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above..
4.1.2.5.b Verify RWST temperature 3.5.4.1 Requirements for Modes 5 and 6 were not specified in NUREG-1431. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 4 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.1.2.6 Boration Systems - Borated Water Source - Operating 4.1.2.6.a.1 Verify borated water source boron concentration Relocation of Frequencies is consistent with intent of TSTF-425. TSTF-425 SR 3.5.4.3 and 3.5.6.3 are not a direct correlation but contain similar actions and frequencies.
4.1.2.6.a.2 Verify borated water source volume Relocation of Frequencies is consistent with intent of TSTF-425. TSTF-425 SR 3.5.4.2 and 3.5.6.2 are not a direct correlation but contain similar actions and frequencies.
4.1.2.6.a.3 Verify boric acid tank solution temperature Relocation of Frequencies is consistent with intent of TSTF-425. TSTF-425 SR 3.5.4.1 and 3.5.6.1 are not a direct correlation but contain similar actions and frequencies.
4.1.2.6.b Verify RWST temperature 3.5.4.1 3.1.3.1 Movable Control Assemblies - Group Height 4.1.3.1.1 Verify individual rod position within group demand limit 3.1.4.1 4.1.3.1.2 Verify rod freedom of movement 3.1.4.2 3.1.3.2 Position Indication Systems - Operating 4.1.3.2 Verify Demand Position Indication System and Digital Rod Position Indication System agree Note, this not applied to NUREG-1431 SR 3.1.7.1 due to event-driven Frequency.
Relocation of HNP frequency, specified as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.1.3.3 Position Indication Systems - Shutdown 4.1.3.3 Verify digital rod position indicators agree with the demand position indicators Note not applied to NUREG-1431 SR 3.1.7.1 due to event-driven Frequency. Relocation of HNP frequency, specified as 18 months, is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 5 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.1.3.4 Rod Drop Time 4.1.3.4 Demonstrate rod drop time of shutdown and control rods NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.1.3.5 Shutdown Rod Insertion Limit 4.1.3.5 Verify each shutdown rod fully withdrawn 3.1.5.1 3.1.3.6 Control Rod Insertion Limits 4.1.3.6 Verify each control bank within insertion limits 3.1.6.2 3.2.1 Axial Flux Difference 3.2.3A 4.2.1.1.a Verify AFD with AFD Monitor Alarm Operable 3.2.3.1 NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.2.1.3 Determine target AFD NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.2.2 Heat Flux Hot Channel Factor (FQ(Z))
4.2.2.2.d.2 Verify measured values of FQ(Z) 3.2.1.1 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor 4.2.3.2 Verify N
H F
3.2.2.1 3.2.4 Quadrant Power Tilt Ratio 4.2.4.1.a Verify QPTR by calculation with alarm Operable 3.2.4.1 4.2.4.2 Verify QPTR using movable incore detectors 3.2.4.2
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 6 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.2.5 DNB Parameters 4.2.5.1 Verify RCS Tavg, Pressurizer pressure, and RCS total flow rate.
3.4.1.1 3.4.1.2 3.4.1.3 4.2.5.2 Verify RCS total flow rate by precision heat balance 3.4.1.4 3.3.1 Reactor Trip System Instrumentation 4.3.1.1, Table 4.3-1 Channel Check (Shiftly) 3.3.1.1 4.3.1.1, Table 4.3-1 Channel Calibration (Daily) 3.3.1.2 4.3.1.1, Table 4.3-1 Channel Calibration (Monthly) 3.3.1.3 4.3.1.1, Table 4.3-1 Channel Calibration (Quarterly)
NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.3.1.1, Table 4.3-1 Channel Calibration (Refueling) 3.3.1.10 3.3.1.12 4.3.1.1, Table 4.3-1 Analog Channel Operational Test (Quarterly) 3.3.1.7 3.3.1.8 4.3.1.1, Table 4.3-1 Analog Channel Operational Test (Refueling) 3.3.1.13 4.3.1.1, Table 4.3-1 Trip Actuating Device Operational Test (Refueling) 3.3.1.14 4.3.1.1, Table 4.3-1 Trip Actuating Device Operational Test (Quarterly) 3.3.1.9 4.3.1.1, Table 4.3-1 Trip Actuating Device Operational Test (Monthly) 3.3.1.4 4.3.1.1, Table 4.3-1 Actuation Logic Test (Monthly) 3.3.1.5 4.3.1.2 Verify Reactor Trip System Response Time 3.3.1.16 3.3.2 Engineered Safety Features Actuation System Instrumentation 4.3.2.1, Table 4.3-2 Channel Check (Shiftly) 3.3.2.1 4.3.2.1, Table 4.3-2 Channel Calibration (Refueling) 3.3.2.9 3.3.5.3
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 7 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 4.3.2.1, Table 4.3-2 Analog Channel Operational Test (Quarterly) 3.3.2.5 4.3.2.1, Table 4.3-2 Trip Actuating Device Operational Test (Monthly) 3.3.2.7 4.3.2.1, Table 4.3-2 Trip Actuating Device Operational Test (Refueling) 3.3.2.8 4.3.2.1, Table 4.3-2 Actuation Logic Test (Monthly) 3.3.2.2 3.3.2.3 3.3.5.2 4.3.2.1, Table 4.3-2 Master Relay Test (Monthly) 3.3.2.4 4.3.2.1, Table 4.3-2 Slave Relay Test (Quarterly) 3.3.2.6 4.3.2.1, Table 4.3-2 Slave Relay Test (Refueling)
NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.3.2.2 Verify ESFAS Response Times 3.3.2.10 3.3.3.1 Radiation Monitoring for Plant Operations 4.3.3.1, Table 4.3-3 Channel Check (Shiftly) 3.3.6.1 3.3.7.1 3.3.8.1 3.4.15.1 4.3.3.1, Table 4.3-3 Channel Calibration (Refueling) 3.3.6.9 3.3.7.9 3.3.8.5 3.4.15.3 3.4.15.4 4.3.3.1, Table 4.3-3 Digital Channel Operational Test (Quarterly) 3.3.6.6 3.3.7.2 3.3.8.2 3.4.15.2
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 8 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.3.4.5.a Remote Shutdown System 4.3.3.5.1, Table 4.3-6 Channel Check (Monthly) 3.3.4.1 4.3.3.5.1, Table 4.3-6 Channel Calibration (Refueling) 3.3.4.3 4.3.3.5.2 Verify control circuit and transfer switch capable of function 3.3.4.2 3.3.3.6 Accident Monitor Instrumentation 4.3.3.6, Table 4.3-7 Channel Check (Monthly) 3.3.3.1 4.3.3.6, Table 4.3-7 Calibration (Refueling) 3.3.3.2 3.4.1.1 Reactor Coolant Loops and Coolant Circulation -
Startup and Power Operation 4.4.1.1 Verify RCS loops in operation 3.4.4.1 3.4.1.2 Reactor Coolant Loops and Coolant Circulation - Hot Standby 4.4.1.2.1 Verify correct breaker alignment 3.4.5.3 4.4.1.2.2 Verify Steam generator secondary side water levels 3.4.5.2 4.4.1.2.3 Verify required RCS loops in operation 3.4.5.1 3.4.1.3 Reactor Coolant Loops and Coolant Circulation - Hot Shutdown 4.4.1.3.1 Verify correct breaker alignment 3.4.6.3 4.4.1.3.2 Verify SG secondary side water level 3.4.6.2 4.4.1.3.3 Verify required RHR or RCS loop operation 3.4.6.1 4.4.1.3.4 Verify locations susceptible to gas accumulation sufficiently filled with water NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 9 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.4.1.4.1 Reactor Coolant Loops and Coolant Circulation -
Cold Shutdown - Loops Filled 4.4.1.4.1.1 Verify SG secondary side water level 3.4.7.2 4.4.1.4.1.2 Verify required RHR loop operation 3.4.7.1 4.4.1.4.1.3 Verify locations susceptible to gas accumulation sufficiently filled with water NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.4.1.4.2 Reactor Coolant Loops and Coolant Circulation -
Cold Shutdown - Loops Not Filled 4.4.1.4.2.1 Verify required RHR loop operation 3.4.8.1 4.4.1.4.2.2 Verify locations susceptible to gas accumulation sufficiently filled with water NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.4.3 Pressurizer 4.4.3.1 Verify pressurizer water level 3.4.9.1 4.4.3.2.c Verify pressurizer heater group capacity 3.4.9.2 3.4.4 Relief Valves 4.4.4.1.a Channel Calibration of actuation instrumentation NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.4.4.1.b Perform cycle of PORV 3.4.11.2 4.4.4.2 Perform cycle of block valve 3.4.11.1 4.4.4.3 Demonstrate accumulator Operable NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 10 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.4.6.1 Reactor Coolant System Leakage - Leakage Detection Systems 4.4.6.1.a, Table 4.3-3 Channel Check (radioactivity monitor) 3.4.15.1 4.4.6.1.a, Table 4.3-3 Digital Channel Operational Test (airborne and particulate radioactivity monitors) 3.4.15.2 4.4.6.1.a, Table 4.3-3 Channel Calibration (airborne and particulate radioactivity monitor) 3.4.15.4 4.4.6.1.b Channel Calibration (Reactor Cavity Sump Level and Flow Monitoring System) 3.4.15.3 3.4.6.2 Reactor Coolant System Operational Leakage 4.4.6.2.1.a Monitor containment airborne gaseous or particulate radioactivity monitor 3.4.15.1 4.4.6.2.1.b Monitor containment sump inventory and Flow Monitoring System NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.4.6.2.1.c Measure controlled leakage to reactor coolant pump seals 3.5.5.1 4.4.6.2.1.d Verify RCS operational leakage 3.4.13.1 4.4.6.2.1.e Monitor Reactor Head Flange Leakoff System NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.4.6.2.2.a Verify PIV leakage 3.4.14.1 4.4.6.2.3 Verify primary to secondary leakage 3.4.13.2 3.4.7 Reactor Coolant System Chemistry 4.4.7, Table 4.4-3 sample Dissolve Oxygen NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.4.7, Table 4.4-3 sample Chloride 4.4.7, Table 4.4-3 sample Fluoride
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 11 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.4.8 Reactor Coolant System Specific Activity 4.4.8, Table 4.4-4 Verify gross specific activity 3.4.16.1 4.4.8, Table 4.4-4 Verify Dose Equivalent I-131 3.4.16.2 4.4.8, Table 4.4-4 Determine 3.4.16.3 3.4.9.1 Pressure/Temperature Limits - Reactor Coolant System 4.4.9.1 Verify RCS pressure, temperature, and heatup and cooldown rates 3.4.3.1 3.4.9.2 Pressure/Temperature Limits - Reactor Coolant System 4.4.9.2.1 Verify RCS pressure, temperature, and heatup and cooldown rates 3.4.3.1 3.4.9.4 Reactor Coolant System Overpressure Protection System 3.4.12 4.4.9.4.1.a Perform Analog Channel Operational Test 3.4.12.8 4.4.9.4.1.b Perform Channel Calibration 3.4.12.9 4.4.9.4.1.c Verify PORV isolation valve open 3.4.12.6 4.4.9.4.2 Verify required vent open 3.4.12.5 3.4.11 Reactor Coolant System Vents 4.4.11.2.a Verify manual isolation valve position NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.4.11.2.b Cycle each vent path valve 4.4.11.2.c Verify flow through vent path 3.5.1 Accumulators - Cold Leg Injection 4.5.1.1.a.1 Verify borated water volume and nitrogen cover pressure 3.5.1.2 3.5.1.3 4.5.1.1.a.2 Verify accumulator isolation valves open 3.5.1.1 4.5.1.1.b Verify boron concentration 3.5.1.4 4.5.1.1.c Verify isolation valve operator power removed 3.5.1.5
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 12 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.5.2 ECCS - Tavg Greater Than or Equal to 350F 4.5.2.a.1 Verify valves in correct position with power removed 3.5.2.1 4.5.2.b.1 Verify ECCS locations susceptible to gas accumulation sufficiently filled with water 3.5.2.3 NUREG-1431 addresses ECCS piping in general. HNP TS was adjusted to address locations susceptible to gas accumulation.
Relocation of this frequency remains consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.5.2.b.2 Verify ECCS valve position 3.5.2.2 HNP TS adjusted to provide footnote: Not required to be met for system vent flow paths opened under administrative control.
Relocation of this frequency remains consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.5.2.d.1 Verify RHR System automatic interlock function 3.4.14.2 4.5.2.d.2 Verify sump suction strainers 3.5.2.8 4.5.2.e.1 Verify ECCS automatic valves actuate automatically 3.5.2.5 4.5.2.e.2 Verify ECCS pumps start automatically 3.5.2.6 4.5.2.g.2 Verify ECCS throttle valve stop position 3.5.2.7 3.5.4 Refueling Water Storage Tank 4.5.4.a.1 Verify RWST water volume 3.5.4.2 4.5.4.a.2 Verify RWST boron concentration 3.5.4.3 4.5.4.b Verify RWST water temperature 3.5.4.1 3.6.1.1 Primary Containment - Containment Integrity 3.6.1.1 4.6.1.1.a Verify all penetrations not capable of automatic isolation is isolated 3.6.3.3 3.6.1.3 Containment Air Locks 4.6.1.3 Verify only one door can be opened at a time 3.6.2.2 3.6.1.4 Containment Systems - Internal Pressure 4.6.1.4 Verify containment pressure 3.6.4A.1
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 13 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.6.1.5 Containment Systems - Air Temperature 4.6.1.5 Verify containment air temperature 3.6.5A.1 3.6.1.7 Containment Systems - Containment Ventilation Systems 4.6.1.7.1 Verify each 42-inch purge makeup and exhaust valve sealed closed and closed 3.6.3.1 4.6.1.7.2 Perform leakage rate testing on each containment purge valve (2-42 inch valves and 2-8 inch valves) 3.6.3.7 3.6.2.1 Containment Spray System 4.6.2.1.a Verify each containment spray valve in correct position 3.6.6A.1 HNP TS adjusted to provide footnote: Not required to be met for system vent flow paths opened under administrative control.
Relocation of this frequency remains consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.6.2.1.c.1 Verify automatic containment spray valves actuate 3.6.6A.5 4.6.2.1.c.2 Verify containment spray pumps automatically start 3.3.6A.6 4.6.2.1.c.3 Verify automatic valves from sump and RWST actuate to correct position 3.6.6A.5 4.6.2.1.d Verify spray nozzles unobstructed 3.6.6A.8 4.6.2.1.e Verify locations susceptible to gas accumulation sufficiently filled with water NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.6.2.2 Spray Additive System 4.6.2.2.a Verify spray additive valves in correct position 3.6.7.1 4.6.2.2.b.1 Verify spray additive tank solution volume 3.6.7.2 4.6.2.2.b.2 Verify spray additive tank solution concentration 3.6.7.3 4.6.2.2.c Verify automatic spray additive valves actuate 3.6.7.4 4.6.2.2.d Verify spray additive flow rate 3.6.7.5
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Similar TSTF-425 SR Number Discussion of Differences 3.6.2.3 Containment Cooling System 4.6.2.3.a.1 Operate containment cooling train fan 3.6.6A.2 4.6.2.3.a.2 Verify containment cooling train cooling water flow 3.6.6A.3 4.6.2.3.b Verify containment cooling trains automatically start 3.6.6A.7 3.6.3 Containment Isolation Valves 4.6.3.2.a Verify 'Phase A' automatic containment isolation valves actuate 3.6.3.8 4.6.3.2.b Verify 'Phase B' automatic containment isolation valves actuate 3.6.3.8 4.6.3.2.c Verify purge makeup and exhaust. and containment vacuum relief valves actuate 3.6.3.8 4.6.3.2.d Verify automatic containment isolation valves receiving an 'S' signal actuate 3.6.3.8 4.6.3.2.e Verify Main Steam Isolation Valves actuate 3.7.2.2 4.6.3.2.f Verify Main Feedwater Isolation Valves actuate 3.7.3.2 3.7.1.2 Auxiliary Feedwater System 4.7.1.2.1.a.1 Demonstrate each motor-driven pump satisfies performance requirements Note not applied to NUREG-1431, SR 3.7.5.2 because Frequency is "In accordance with the Inservice Test Program." HNP Frequency is "At least once per 92 days on a STAGGERED TEST BASIS." Relocation of this frequency is consistent with the intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.7.1.2.1.a.2 Demonstrate turbine-driven pump satisfies performance requirements 4.7.1.2.1.b.1 Verify AFW valves in correct position 3.7.5.1 4.7.1.2.1.b.2 Verify CST suction isolation valves open 3.7.5.1 4.7.1.2.1.c.3 Verify AFW automatic valves automatically actuate 3.7.5.3 4.7.1.2.1.c.1 Verify motor-driven AFW pumps start automatically 3.7.5.4 4.7.1.2.1.c.2 Verify turbine-driven AFW pump starts automatically 3.7.5.4
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Similar TSTF-425 SR Number Discussion of Differences 3.7.1.3 Condensate Storage Tank (CST) 4.7.1.3.1 Verify CST level 3.7.6.1 4.7.1.3.2 Verify each Emergency Service Water Valve supplying AFW is open 3.7.8.1 3.7.1.4 Plant Systems - Specific Activity 4.7.1.4 Table 4.7-1 Gross Radioactivity Determination or Isotropic Analysis for Dose Equivalent I-131 3.7.18.1 4.7.1.4 Table 4.7-1 Isotropic Analysis for Dose Equivalent I-131 (gross radioactivity indicates 10% of limit) 3.7.18.1 3.7.2 Steam Generator Pressure/Temperature Limitation 4.7.2 Verify steam generator pressure NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.7.3 Component Cooling Water 4.7.3.a Verify CCW valves in correct position 3.7.7.1 4.7.3.b.1 Verify automatic CCW valves automatically actuate 3.7.7.2 4.7.3.b.2 Verify CCW pumps automatically start 3.7.7.3 4.7.3.b.3 Verify each automatic valve serving gross failed fuel detector and sample system heat exchangers automatically actuates 3.7.7.2 3.7.4 Emergency Service Water System 4.7.4.a Verify each valve in correct position 3.7.8.1 4.7.4.b.1 Verify each automatic valve automatically actuates 3.7.8.2 4.7.4.b.2 Verify each emergency service water pump and each emergency service water booster pump automatically starts 3.7.8.3 3.7.5 Ultimate Heat Sink (UHS) 4.7.5 Verify UHS water temperature and water level 3.7.9.1 3.7.9.2
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 16 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.7.6 Control Room Emergency Filtration System 4.7.6.a Operate each train 3.7.10.1 4.7.6.b.1 Verify cleanup system satisfies in-place penetration and bypass leakage testing acceptance criteria Note not applied to NUREG-1431, SR 3.7.10.2 because Frequency is in accordance with the Ventilation Filter Testing Program (VFTP).
HNP Frequency is "18 months." Relocation of these frequencies is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.7.6.b.2 Verify methyl iodide penetration within limits 4.7.6.d.1 Verify HEPA filter and charcoal adsorber pressure drop 4.7.6.d.2 Verify system automatically actuates 3.7.10.3 4.7.6.d.3 Verify system maintains positive pressure 3.7.10.4 4.7.6.d.4 Verify heater capacity Note not applied to NUREG-1431, SR 3.7.10.2 because Frequency is in accordance with the Ventilation Filter Testing Program (VFTP).
HNP Frequency is "18 months." Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 3.7.7 Reactor Auxiliary Building (RAB) Emergency Exhaust System 4.7.7.a Operate each train 3.7.12.1 4.7.7.b.1 Verify cleanup system satisfies in-place penetration and bypass leakage testing acceptance criteria Note not applied to NUREG-1431, SR 3.7.12.2 because Frequency is in accordance with the Ventilation Filter Testing Program (VFTP).
HNP Frequency is "18 months." Relocation of these frequencies is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.7.7.b.2 Verify methyl iodide penetration within limits 4.7.7.d.1 Verify HEPA filter and charcoal adsorber pressure drop 4.7.7.d.2 Verify system automatically actuates 3.7.12.3 4.7.7.d.3 Verify system maintains positive pressure 3.7.12.4
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Similar TSTF-425 SR Number Discussion of Differences 4.7.7.d.4 Verify filter cooling bypass valve locked NUREG-1431 does not specify a similar requirement. NUREG-1431, SR 3.7.12.5 requires verification that the filter bypass damper can be closed. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.7.7.d.5 Verify heater capacity Note not applied to NUREG-1431, SR 3.7.12.2 because Frequency is in accordance with the Ventilation Filter Testing Program (VFTP).
HNP Frequency is "18 months." Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 3.7.13 Essential Services Chilled Water System 4.7.13.1 Verify non-essential portions automatically isolate NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.7.13.2 Verify systems starts automatically 3.7.14 Fuel Storage Pool Boron Concentration 4.7.14 Verify boron concentration 3.7.16.1 3.8.1.1 AC Sources - Operating 3.8.1 4.8.1.1.1.a Verify correct breaker alignment 3.8.1.1 4.8.1.1.1.b Verify transfer of power from offsite circuit to alternate circuit 3.8.1.8 4.8.1.1.2.a.1 Verify each day tank level 3.8.1.4 4.8.1.1.2.a.2 Verify main fuel oil storage tank level 3.8.3.1 4.8.1.1.2.a.3 Verify fuel oil transfer system operates 3.8.1.6 4.8.1.1.2.a.4 Verify each DG starts from standby conditions/steady state 3.8.1.2 4.8.1.1.2.a.5 Verify each DG is synchronized and loaded 3.8.1.3 4.8.1.1.2.a.6 Verify air start receiver pressure 3.8.3.4
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 18 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 4.8.1.1.2.a.7 Verify DG is aligned to associated emergency buses NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.8.1.1.2.b.1 Check for and remove accumulated water from day tank 3.8.1.5 4.8.1.1.2.b.2 Check/remove accumulated water from fuel oil storage tank 3.8.3.5 4.8.1.1.2.d Verify total particulate from sample of fuel oil storage tank Note not applied to NUREG-1431, SR 3.8.3.2 because Frequency is in accordance with the Diesel Fuel Oil Testing Program. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.8.1.1.2.e Verify each DG starts from standby conditions/quick start 3.8.1.7 4.8.1.1.2.f.2 Verify DG rejects load 1078 KW, stabilizes without tripping any safety-related load NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.8.1.1.2.f.3 Verify interval between each timed load block 3.8.1.18 4.8.1.1.2.f.4 Verify on loss of offsite power signal, de-energization, load shedding and auto-start 3.8.1.11 4.8.1.1.2.f.5 Verify DG starts on safety injection test signal 3.8.1.12 4.8.1.1.2.f.6 Verify on LOOP in conjunction with ECCS initiation signal 3.8.1.19 4.8.1.1.2.f.7 Verify each DG operates for > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.8.1.14 4.8.1.1.2.f.9 Verify DG capability to synchronize with offsite power, transfer loads to offsite power and proceed through shutdown sequence 3.8.1.16 4.8.1.1.2.f.11 Verify DG rejects load between 6200 and 6400 KW 3.8.1.9 3.8.1.10 4.8.1.1.2.f.12 Verify ECCS initiation signal overrides test mode 3.8.1.17
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 19 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 4.8.1.1.2.f.13 Verify DG automatic trips bypassed on ECCS initiation signal 3.8.1.13 4.8.1.1.2.f.14 Verify each DG starts from standby conditions/quick restart 3.8.1.15 4.8.1.1.2.g Verify simultaneous DG starts 3.8.1.20 4.8.1.1.2.h.1 Drain each main fuel oil storage tank, remove sediment and clean Note not applied to NUREG-1431, SR 3.8.3.2 because Frequency is in accordance with the Diesel Fuel Oil Testing Program. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.8.1.1.2.h.2 Perform pressure test of diesel fuel oil piping NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 3.8.2.1 DC Sources - Operating 4.8.2.1.a.1 Verify parameters in Table 4.8-2 meet Category A limits HNP has not incorporated generic change TSTF-360, 'DC Electrical rewrite.' TSTF-425 relocates the frequencies of many of the DC Sources - Operating and Battery Parameter SRs. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 4.8.2.1.a.2 Verify total battery terminal voltage 4.8.2.1.b.1 Verify parameters in Table 4.8-2 meet Category B limits 4.8.2.1.b.2 Verify no visible corrosion at terminals and connectors 4.8.2.1.b.3 Verify average electrolyte temperature of 10 connected cells 4.8.2.1.c.1 Verify cells, cell plates and racks show no physical damage 4.8.2.1.c.2 Verify cell-to-cell and terminal connections clean and tight 4.8.2.1.c.3 Verify resistance of cell-to-cell and terminal connections 4.8.2.1.c.4 Verify battery charger capacity 3.8.4.2
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 20 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 4.8.2.1.d Verify battery capacity is adequate to maintain emergency loads 3.8.4.3 4.8.2.1.e Verify battery capacity during performance discharge test 3.8.6.6 3.8.3.1 Onsite Power Distribution - Operating 4.8.3.1 Verify correct breaker alignment/power to distribution subsystems and indicated voltage 3.8.9.1 3.8.7.1 3.8.3.2 Onsite Power Distribution - Shutdown 3.8.10 4.8.3.2 Verify correct breaker alignment/power to distribution subsystems and indicated voltage 3.8.10.1 3.8.8.1 3.8.4.1 Containment Penetration Conductor Overcurrent Protective Devices 4.8.4.1.a.1.a Channel Calibration of protective relays Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.8.4.1.a.1.b System functional test 4.8.4.1.a.2 Functionally testing representative sample 4.8.4.1.b Subject each breaker to inspection and preventative maintenance 3.8.4.2 Motor-Operated Valves Thermal Overload Protection 4.8.4.2.a Perform Trip Actuation Device Operational Test Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above 3.9.1.a Boron Concentration 4.9.1.1 Verify boron concentration 3.9.1.1 4.9.1.2 Verify valves closed 3.9.2.1 3.9.2 Refueling Operations - Instrumentation 4.9.2.a Channel Check 3.9.3.1 4.9.2.b Channel Calibration 3.9.3.2 3.9.4 Containment Building Penetrations 4.9.4.a Verify each containment penetration in required status 3.9.4.1 4.9.4.b Verify containment purge and containment pre-entry purge makeup and exhaust valve automatically actuate 3.9.4.2
U.S. Nuclear Regulatory Commission HNP-16-040 Attachment 2 Page 21 of 23 HNP TS Surveillance Requirement (SR)
Similar TSTF-425 SR Number Discussion of Differences 3.9.8.1 Residual Heat Removal and Coolant Circulation - High Water Level 4.9.8.1.1 Verify one RHR loop 3.9.5.1 4.9.8.1.2 Verify locations susceptible to gas accumulation sufficiently filled with water NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.9.8.2 Residual Heat Removal and Coolant Circulation - Low Water Level 4.9.8.2.1 Verify one RHR loop and flow rate with level at or above vessel flange 3.9.6.1 NUREG-1431 does not differentiate between above or below vessel flange. Relocation of these frequencies is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.9.8.2.2 Verify one RHR loop and flow rate with level below vessel flange 4.9.8.2.3 Verify locations susceptible to gas accumulation sufficiently filled with water NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.9.9 Containment Ventilation Isolation System 4.9.9 Verify automatic isolation on actuation signal and ability to close from control switch 3.3.6.4 3.3.6.6 3.9.10 Water Level - Reactor Vessel 4.9.10 Verify water level 3.9.7.1 3.9.11 Water Level - New and Spent Fuel Pools 4.9.11 Verify water level 3.7.15.1 3.9.12 Fuel Handling Building Emergency Exhaust System 4.9.12.a Operate each train 3.7.13.1 4.9.12.b.1 Verify cleanup system satisfies in-place penetration and bypass leakage testing acceptance criteria Note not applied to NUREG-1431, SR 3.7.13.2 because Frequency is in accordance with the Ventilation Filter Testing Program (VFTP).
4.9.12.b.2 Verify methyl iodide penetration within limits
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Similar TSTF-425 SR Number Discussion of Differences 4.9.12.d.1 Verify HEPA filter and charcoal adsorber pressure drop HNP Frequency is "18 months." Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.9.12.d.2 Verify system automatically actuates 3.7.13.3 4.9.12.d.3 Verify system maintains negative pressure 3.7.13.4 4.9.12.d.5 Verify heater capacity Note not applied to NUREG-1431, SR 3.7.13.2 because Frequency is in accordance with the Ventilation Filter Testing Program (VFTP).
HNP Frequency is "18 months." Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.10.1 Special Test Exceptions - Shutdown Margin 4.10.1.1 Verify position of shutdown and control rods NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.10.2 Special Test Exceptions - Group Height, Insertion, and Power Distribution Limits 4.10.2.1 Verify Thermal Power level 85%
NUREG-1431 does not specify a similar requirement. Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
4.10.2.2.a Verify FQ(Z) within limits 4.10.2.2.b Verify N
H Fwithin limits 3.10.3 Special Test Exceptions - Physics Tests 4.10.3.1 Verify Thermal Power 5%
3.1.8.3 4.10.3.3 Verify Tavg 3.1.8.2 3.10.4 Special Test Exceptions - Reactor Coolant Loops 4.10.4.1 Verify Thermal Power < P-7 3.4.19.1
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Similar TSTF-425 SR Number Discussion of Differences 3.10.5 Special Test Exceptions - Position Indication System -
Shutdown 4.10.5 Verify Demand Position Indication System and Digital Rod Position Indication System agree Note not applied to NUREG-1431, SR 3.1.7.1, due to event-driven Frequency. HNP Frequency is "24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />." Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
3.11.2.5 Explosive Gas Mixture 4.11.2.5 Verify hydrogen and oxygen in Gaseous Radwaste Treatment System within limits These requirements are typically relocated to the Explosive Gas and Storage Tank Radioactivity Monitoring Program (NUREG-1431, 5.5.12) during ITS conversion. The HNP Frequency is "At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />." Relocation of this frequency is consistent with intent of TSTF-425 and does not qualify for the exclusions discussed above.
6.8.4.p Programs (Surveillance Frequency Control Program) 5.5.18