ML050770384

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Request for Amendment to Facility Operating Licenses NPF-41, NPF-51 and NPF-74 to License Condition 2.F (2.G in Unit 3) and Request for Amendment to Technical Specifications
ML050770384
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 03/04/2005
From: Mauldin D
Arizona Public Service Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05223-CDM/SAB/RKR
Download: ML050770384 (73)
v • d • e


Text

LAF 10 CFR 50.90 David Mauldin Vice President Mail Station 7605 Palo Verde Nuclear Nuclear Engineering TEL (623) 393-5553 P.O. Box 52034 Generating Station and Support FAX (623) 393-6077 Phoenix, AZ 85072-2034 102-05223-CDM/SAB/RKR March 4, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Request for Amendment to Facility Operating Licenses NPF-41, NPF-51 and NPF-74 to License Condition 2.F (2.G in Unit 3) and Request for Amendment to Technical Specifications:

1.4, "Frequency,"

2.1.1, "Reactor Core SLs,"

3.1.10, "Special Test Exceptions (STE) - MODES 1 and 2,"

3.3.1, "Reactor Protective System (RPS)

Instrumentation - Operating,"

3.4.3, "RCS Pressure and Temperature (P/T) Limits,"

3.7.2, "Main Steam Isolation Valves (MSIVs),"

3.7.3, "Main Feedwater Isolation Valves (MFIVs),"

3.8.1, "AC Sources - Operating,"

3.8.4, "DC Sources - Operating,"

3.8.6, "Battery Cell Parameters," and 5.5.9, "Steam Generator (SG) Tube Surveillance Program" Pursuant to 10 CFR 50.90, Arizona Public Service Company (APS) hereby requests an amendment to Facility Operating Licenses NPF-41, NPF-51 and NPF-74 to License Condition 2.F (2.G in Unit 3) and to Technical Specifications Sections 1.4, "Frequency,"

2.1.1, "Reactor Core SLs," 3.1.10, "Special Test Exceptions (STE) - MODES I and 2,"

3.3.1, "Reactor Protective System (RPS) Instrumentation - Operating," 3.4.3, "RCS Pressure and Temperature (P/T) Limits," 3.7.2, "Main Steam Isolation Valves (MSIVs),"

3.7.3, 'Main Feedwater Isolation Valves (MFIVs)," 3.8.1, "AC Sources - Operating,"

3.8.4, UDC Sources - Operating," 3.8.6, "Battery Cell Parameters," and 5.5.9, "Steam Generator (SG) Tube Surveillance Program." The proposed changes are considered administrative and/or editorial.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

  • Comanche Peak
  • Diablo Canyon
  • Palo Verde
  • Wolf Creek poo01

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Request for Amendment to Operating License and Technical Specifications Page 2 The following changes are being proposed:

  • License Condition 2.F (2.G in Unit 3) is being deleted. The reporting requirements in this License Condition are also governed by 10 CFR 50.72 and 50.73.
  • TSs 1.4 and 3.4.3 are being changed to correct editorial errors.
  • TSs 2.1.1 and 3.3.1 are being changed to remove the reference to departure from nucleate boiling ratios (DNBR) based on operating cycle, since only one of the listed DNBR values is now valid.
  • TS 3.1.10 is being changed to correct an inconsistency between the limiting condition for operation and the TS Bases.
  • TS 3.7.2 and 3.7.3 are being changed to correct the applicability for these specifications.
  • A note is being added to a surveillance requirement in TS 3.8.1.

TS 3.8.4 and 3.8.6 are being changed to remove the reference to AT&T batteries.

  • TS 5.5.9 is being changed to correct the reference for NRC notification. provides a detailed description of the proposed changes. Attachment 1 provides the existing TS pages marked up to show the proposed change. Attachment 2 provides revised (clean) TS pages. Associated TS Bases changes, provided for information in Attachment 3, would be implemented at the same time as the approved amendment.

The deletion of License Condition 2.F (2.G in Unit 3) in this License Amendment Request (LAR) is similar to changes approved by the NRC for Fermi 2, on May 16, 2003, Comanche Peak Steam Electric Station, Units 1 and 2 on May 15, 2003, Wolf Creek Generating Station, on September 24, 2001, and South Texas Project, Units 1 and 2 on August 16, 2001.

Arizona Public Service Company (APS) is submitting the change to License Condition 2.F (2.G in Unit 3) of this LAR in conjunction with an industry consortium of six stations as a result of a mutual agreement known as Strategic Teaming and Resource Sharing (STARS). The STARS group consists of the six stations operated by TXU Generation Company LP, Union Electric Company, Wolf Creek Nuclear Operating Corporation, Pacific Gas and Electric Company, STP Nuclear Operating Company, and Arizona Public Service Company. The change has been approved by the NRC for Wolf Creek Nuclear Operating Corporation, STP Nuclear Operating Company, and TXU Generation Company LP. Due to differences between the STARS plants, there may be some differences in the plant LARs, particularly for the information provided in Enclosure 2.

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Request for Amendment to Operating License and Technical Specifications Page 3 Based on the responses to the three criteria provided for determining whether a significant hazard consideration exists as stated in 10 CFR 50.92, APS has concluded that the proposed amendment involves no significant hazard consideration.

In accordance with the PVNGS Quality Assurance Program, the Plant Review Board and the Offsite Safety Review Committee have reviewed and concurred with this proposed amendment. By copy of this letter, this submittal is being forwarded to the Arizona Radiation Regulatory Agency (ARRA) pursuant to 10CFR 50.91 (b)(1).

The changes proposed in this LAR are not required to address an immediate safety concern. APS requests the LAR be made effective upon NRC issuance, to be implemented within 60 days from the date of issuance.

No commitments are being made to the NRC by this letter. If you have any questions, please contact Thomas N. Weber at (623) 393-5764.

Sincerely, CDM/SAB/RKR/kg

Enclosures:

1. Notarized affidavit
2. Licensee's evaluation of the proposed change Attachments:
1. Proposed Operating License and Technical Specification Changes (mark-up)
2. Proposed Technical Specification pages (retyped)
3. Changes to TS Bases Pages (For Information Only) cc:

B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager G. G. Warnick NRC Senior Resident Inspector for PVNGS J. N. Donohew NRC A. V. Godwin Arizona Radiation Regulatory Agency (ARRA)

ENCLOSURE 1 AFFIDAVIT

STATE OF ARIZONA

)

) ss.

COUNTY OF MARICOPA )

1, David Mauldin, represent that I am Vice President Nuclear Engineering and Support, Arizona Public Service Company (APS), that the foregoing document has been signed by me on behalf of APS with full authority to do so, and that to the best of my knowledge and belief, the statements made therein are true and correct.

David Mauldin Sworn To Before Me This L2 Day Of (;)2QC/)

, 2005.

OFFICALS Not lic Susie Lynn Ergish NOTARY PUBLIC -STATE of ARIZONA MARICOPA COUNTY Y Cow EXPIRES Ju14.2007 Notary Commission Stamp

ENCLOSURE 2 ARIZONA PUBLIC SERVICE COMPANY'S EVALUATION

Subject:

Request for Amendment to Facility Operating Licenses NPF-41, NPF-51 and NPF-74 to License Condition 2.F (2.G in Unit 3) and Request for Amendment to Technical Specifications:

1.4, "Frequency,"

2.1.1, "Reactor Core SLs,"

3.1.10, "Special Test Exceptions (STE)-MODES I and 2,"

3.3.1, "Reactor Protective System (RPS)

Instrumentation - Operating,"

3.4.3, "RCS Pressure and Temperature (PIT) Limits,"

3.7.2, "Main Steam Isolation Valves (MSIVs),"

3.7.3, "Main Feedwater Isolation Valves (MFIVs),"

3.8.1, "AC Sources - Operating,"

3.8.4, "DC Sources - Operating,"

3.8.6, "Battery Cell Parameters," and 5.5.9, "Steam Generator (SG) Tube Surveillance Program"

1. DESCRIPTION
2. PROPOSED CHANGE
3. BACKGROUND
4. TECHNICAL ANALYSIS
5. REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria
6. ENVIRONMENTAL CONSIDERATION
7. PRECEDENT
8. REFERENCES E2-1

1.0 DESCRIPTION

This letter is a request from Arizona Public Service Company (APS) to amend Operating Licenses NPF-41, NPF-51, and NPF-74 for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, respectively.

The proposed changes would revise Facility Operating License Condition 2.F (2.G in Unit 3) and to Technical Specifications (TS) Sections 1.4, "Frequency," 2.1.1, "Reactor Core SLs," 3.1.10, "Special Test Exceptions (STE)-MODES 1 and 2," 3.3.1, "Reactor Protective System (RPS) Instrumentation - Operating," 3.4.3, "RCS Pressure and Temperature (P/T) Limits," 3.7.2, "Main Steam Isolation Valves (MSIVs)," 3.7.3, "Main Feedwater Isolation Valves (MFIVs)," 3.8.1, "AC Sources - Operating," 3.8.4, "DC Sources - Operating," 3.8.6, "Baftery Cell Parameters," and 5.5.9, "Steam Generator (SG) Tube Surveillance Program." The proposed changes are considered administrative and/or editorial. License Condition 2.F (2.G in Unit 3) is being deleted.

The reporting requirements in this License Condition are also governed by 10 CFR 50.72 and 50.73. The changes to TSs 1.4 and 3.4.3 correct editorial errors. The changes to TSs 2.1.1 and 3.3.1 remove the reference to departure from nucleate boiling ratios (DNBR) based on operating cycle, since only one of the listed DNBR values is now valid. The changes to TS 3.7.2 and 3.7.3 correct the applicability for these specifications. The change to TS 3.8.1 adds a note to a surveillance requirement. The changes to TS 3.8.4 and 3.8.6 remove the reference to AT&T batteries. The changes to TS 5.5.9 correct the reference for NRC notification.

2.0 PROPOSED CHANGE

The proposed change will revise:

Operating License Condition 2.F (2.G in Unit 3)

Deleted the following License Condition:

Unit 1

2. uF Except as otherwise provided in the Technical Specifications or the Environmental Protection Plan, APS shall report any violations of the requirements contained in Section 2.C of this license in the following manner: Initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in accordance with the provisions of 10 CFR 50.72 with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c) and (e)."

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Units 2 and 3

2. "F (G in Unit 3).

Except as otherwise provided in the Technical Specifications or the Environmental Protection Plan, APS shall report any violations of the requirements contained in Section 2.C of this license in the following manner: Initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c) and (e);"

from 2.1.1.1.

Shutdown reactivity equivalent to at least the highest estimated CEA worth (of those CEAs actually withdrawn) is available for trip insertion" and new surveillance requirement "SR 3.1.10.2 Verify that the position of each CEA not fully inserted is within the acceptance criteria for available negative reactivity addition" with a two hour frequency. Change in format also added item a labeling to first item.

from Tables 3.3.1-1, Function 15.

  • Technical Specification 3.7.2 Revised applicability for this specification from "MODES 2, 3, and 4 except when all MSIVs are closed" to "MODES 2, 3, and 4 except when all MSIVs are closed and deactivated."

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  • Technical Specification 3.7.3 Revised applicability for this specification from "MODES 1, 2, 3, and 4 except when MFIV is closed or isolated by a closed power operated valve" to "MODES 1, 2, 3, and 4 except when MFIV is closed and deactivated or isolated by a closed and deactivated power operated valve."

"4. The steady state voltage and frequency limits are analyzed values and have not been adjusted for instrument error."

Technical Specification 3.8.4

1. Revised SR 3.8.4.1 from "Verify battery terminal voltage is Ž129 V on float charge (low specific gravity cells) or 2131 V on float charge (AT&T)" to "Verify battery terminal voltage is 2129 V on float charge."
2. Revised SR 3.8.4.8 from 'Verify battery capacity is 280% (low specific gravity cells) or 290% (AT&T) of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test" to "Verify battery capacity is 280% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test."
3. Deleted the asterisk at the end of SR 3.8.4.8 and the asterisk note, "* The requirement to perform SR 3.8.4.8 for the Unit 1 batteries A, B, and C is waived until entry into MODE 4 coming out of the ninth refueling outage for Unit 1 (1 R09)" at the bottom of page 3.8.4-4.
1. Revised the title of Table 3.8.6-1 from "(page 1 of 2) (Low Specific Gravity Cells) Battery Surveillance Requirements" to "(page 1 of 1) Battery Surveillance Requirements."
2. Deleted "Table 3.8.6-1 (page 2 of 2) (AT&T) Battery Surveillance Requirements."
1. Revised the requirement for NRC notification in Tables 5.5.9-2 and 5.5.9-3 from "pursuant to 10 CFR 50.72 (b)(2)" to "pursuant to 10 CFR 50.72 (b)(3)"

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3.0 BACKGROUND

Operating License Condition 2.F (2.G in Unit 3)

Operating License Condition 2.F (2.G in Unit 3), provides for initial notification with written follow-up of any violations of requirements contained in Condition 2.C of the PVNGS Facility Operating Licenses. The Nuclear Regulatory Commission's requirements for immediate notification with written follow-up requirements (Licensee Event Reports) of events at operating nuclear power reactors are stated in 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors" and 10 CFR 50.73, "Licensee event report system." Thus, the requirements of PVNGS License Condition 2.F (2.G in Unit 3) are adequately governed by the requirements of 10 CFR 50.72 and 10 CFR 50.73.

Technical Specification 1.4 This is an editorial change only that maintains the format of the TS.

Technical Specification 2.1.1 Technical Specification 2.1.1 provides the safety limits for Departure from Nucleate Boiling Ratio (DNBR). As part of Amendment 133 to the PVNGS Operating License, the minimum DNBR was revised based on Unit operating cycle, "'1.30 (through operating cycle 10)" and "a1.34 (operating cycle 11 and later)." All three PVNGS units have completed operating cycle 10. Therefore, the reference to the minimum DNBR through operating cycle 10 (Ž1.30) is no longer required.

Technical Specification 3.1.10 Technical Specification 3.1.10 permits relaxation of existing LCOs to allow the performance of certain PHYSICS TESTS. These tests are conducted to determine specific reactor core characteristics. The Bases for this specification states that "Even if an accident occurs during PHYSICS TESTS with one or more LCOs suspended, fuel damage criteria are preserved because the limits on power distribution and shutdown capability are maintained during PHYSICS TESTS." The limits on power distribution are maintained by TSs 3.2.1, "Linear Heat Rate (LHR)" and 3.2.4 "Departure from Nucleate Boiling Ratio (DNBR)." However, there are no explicit requirements maintaining shutdown capability. The change to TS 3.1.10 corrects this inconsistency. This change is also consistent with the requirements in TS 3.1.9.

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Technical Specification 3.3.1 Technical Specification 3.3.1, Tables 3.3.1-1 provides the minimum trip setpoint for Departure from Nucleate Boiling Ratio (DNBR). As part of Amendment 133 to the PVNGS Operating License, the minimum DNBR was revised based on Unit operating cycle, "21.30 (through operating cycle I Q)" and "21.34 (operating cycle 11 and later)."

All three PVNGS units have completed operating cycle 10. Therefore, the reference to the minimum DNBR through operating cycle 10 (Ž1.30) is no longer required.

Technical Specification 3.4.3 This is an editorial change only that corrects the parameter for the heatup rate.

Technical Specifications 3.7.2 and 3.7.3 Technical Specifications 3.7.2 and 3.7.3 provide the operability requirements for Main Steam Isolation Valves (MSIVs) and the Main Feedwater Isolation Valves (MFIVs),

respectively. The required action for an inoperable valve requires that the valve be closed and then verified closed every 7 days. In some cases closing the valve removes the LCO required actions from the applicability for the specification. The changes to the applicability correct this conflict.

Technical Specification 3.8.1 As part of Amendment 129 to the PVNGS Operating License, a note was added to several SRs in TS 3.8.1, except SR 3.8.1.2, that verified voltage and frequency. Even though SR 3.8.1.2 verifies voltage and frequency, the note was inadvertently omitted from SR 3.8.1.2. The changes correct this inconsistency.

Technical Specifications 3.8.4 and 3.8.6 APS has replaced the AT&T batteries with low specific gravity batteries in all three units.

This change removes the requirements and references to the AT&T batteries from the TS.

As part of the replacement of the AT&T batteries, PVNGS received a one-time deferral from the requirement to perform a performance discharge test on the Unit 1 AT&T batteries until startup from the ninth Unit 1 refueling outage. The AT&T batteries were replaced prior to startup from the ninth Unit 1 refueling outage. Therefore, the one-time deferral no longer applies and the note is being deleted.

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Technical Specification 5.5.9 Tables 5.5.9-2 and 5.5.9-3 require NRC notification in accordance with 10 CFR 50.72 when the condition of the nuclear power plant, including its principal safety barriers, are seriously degraded (e.g., defective steam generator tubes). Prior to January 23, 2001, this requirement was in 10 CFR 50.72 (b)(2). A rule change was issued for 10 CFR 50.72 on January 23, 2001. As part of the rule change, the reporting requirement for this criteria was changed to an 8-hour non-emergency report in 10 CFR 50.72 (b)(3).

Therefore, this change corrects NRC notification requirements based on the January 23, 2001 rule change to 10 CFR 50.72 (65 FR 63786, 10/25/00).

4.0 TECHNICAL ANALYSIS

Operating License Condition 2.F (2.G in Unit 3)

Operating License Condition 2.C lists requirements regarding Maximum Thermal Power Level, Technical Specifications and Environmental Protection Plan, Antitrust, and Fire Protection (Units 1 and 2 only). Condition 2.F (2.G in Unit 3) requires that PVNGS notify the NRC of violations of the conditions in Condition 2.C within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and submit a report within 30 days. However, this reporting requirement is adequately addressed by the requirements identified in 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors." and 10 CFR 50.73, "Licensee event report system.' Since Condition 2.F (2.G in Unit 3) is redundant, the Condition is not required.

Operating License Condition 2.F (2.G in Unit 3) can be deleted for the following reasons:

Deviations from the conditions regarding Maximum Thermal Power (2.C.(1)),

Technical Specifications and Environmental Protection Plan (2.C.(2)), and Fire Protection (Unit 1 - 2.C.(7) and Unit 2 - 2.C.(6)) are adequately addressed by the requirements of 10 CFR 50.72 and 50.73.

Condition 2.C.(3) regarding Antitrust is an administrative issue and has no safety significance. Consequently, it is not relevant to the proposed elimination of the reporting and notification requirements in Condition 2.F (2.G in Unit 3).

Technical Specification 1.4 This is an editorial change only that maintains the format of the TS.

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Technical Specification 2.1.1 Technical Specification 2.1.1 provides the safety limits for Departure from Nucleate Boiling Ratio (DNBR). As part of Amendment 133 to the PVNGS Operating License, the minimum DNBR was revised based on Unit operating cycle, "21.30 (through operating cycle 10)" and "Ž1.34 (operating cycle 11 and later).' All three PVNGS units have completed operating cycle 10. The DNBR based on unit operating cycle is no longer required. Therefore, the reference to the minimum DNBR through operating cycle 10 (Ž1.30) is no longer required.

Technical Specification 3.1.10 Technical Specification 3.1.1 0 allows the suspension of existing TS LCOs to allow the performance of PHYSICS TESTS. These tests are conducted to determine specific reactor core characteristics. Technical Specification Bases 3.1.10 states that "Even if an accident occurs during PHYSICS TESTS with one or more LCOs suspended, fuel damage criteria are preserved because the limits on power distribution and shutdown capability are maintained during PHYSICS TESTS." Per TS Bases 3.1.10, the limits on power distribution are maintained by TSs 3.2.1, "Linear Heat Rate (LHR)" and 3.2.4 "Departure from Nucleate Boiling Ratio (DNBR)." NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," 3.1.10 included the requirement to verify shutdown margin (SDM). During the conversion to the improved TS, verification of SDM in Modes 1 and 2 was removed by Technical Specification Task Force (TSTF)

Standard Technical Specification Change Traveler, TSTF-67. This resulted in TS 3.1.10 not including explicit requirements for maintaining shutdown capability. This change will ensure that shutdown capability is maintained during PHYSICS TESTS.

This change is also consistent with the requirements of TS 3.1.9, "Special Test Exceptions (STE) - SHUTDOWN MARGIN (SDM)."

Technical Specification 3.3.1 Technical Specification 3.3.1, Table 3.3.1-1 provides the minimum trip setpoint for Departure from Nucleate Boiling Ratio (DNBR). As part of Amendment 133 to the PVNGS Operating License, the minimum DNBR was revised based on Unit operating cycle, Ž1.30 (through operating cycle 10)" and "Ž1.34 (operating cycle 11 and later)."

All three PVNGS units have completed operating cycle 10. The DNBR based on unit operating cycle is no longer required. Therefore, the reference to the minimum DNBR through operating cycle 10 (21.30) is no longer required.

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Technical Specification 3.4.3 This is an editorial change only that corrects the parameter for the heatup rate. The heat rates in Table 3.4.3-1 are in ".F/HR." One of the heatup rates in the Table only had a parameter of "'F." This change corrects that omission.

Technical Specifications 3.7.2 and 3.7.3 The purpose of the MFIVs is to isolate Main Feedwater (MFW) flow to the secondary side of the steam generators following a High Energy Line Break (HELB). Closure of the MFIVs terminates flow to both steam generators, terminating the event for Feedwater Line Breaks (FWLBs) occurring upstream of the MFIVs. The consequences of events occurring in the main steam lines or in the MFW lines downstream of the MFIVs will be mitigated by their closure. Closure of the MFIVs effectively terminates the addition of feedwater to an affected steam generator, limiting the mass and energy release for Steam Line Breaks (SLBs) or FWLBs inside containment, and reducing the cooldown effects for SLBs.

The LCO for TS 3.7.3 states that "Four economizer MFIVs and four downcomer MFIVs shall be OPERABLE" with the applicability "MODES 1, 2, 3, and 4 except when MFIV is closed or isolated by a closed power operated valve." Condition A, "One or more MFIVs inoperable" requires that the inoperable MFIV(s) be closed or isolated within "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" and verified closed or isolated "Once per 7 days." Condition B, "Two valves in the same flow path inoperable" requires that the affected flow path be isolated within "8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />" and verify inoperable MFIV is closed or isolated "Once per 7 days." However, closing the inoperable valve removes the valve from the applicability for the LCO, removing the valve from the requirement to periodically verify that the valve is closed.

The NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," applicability for this LCO includes the bracketed words "[and deactivated]."

During the conversion to the improved TS, APS did not include the bracketed words in the applicability for this LCO. In the original PVNGS TS the requirement to close and deactivate the valves was part of the action and during the conversion it was relocated to the TS Bases.

Based on the discussion above, the requirement to deactivate the valve should have been relocated to the applicability instead of the Actions discussion in the TS Bases.

Adding "and deactivated" to the applicability would correct the inconsistency between the current applicability and required action. Also, changing the applicability to exclude the MFIV when it is closed and deactivated ensures that the isolation function of the MFIV is maintained, the MFIV cannot be inadvertently opened, and, therefore, a weekly check that the MFIV is closed is not necessary.

The purpose of the MSIVs is to isolate steam flow from the secondary side of the steam generators following a HELB. MSIV closure terminates flow from the unaffected (intact)

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steam generator. One MSIV is located in each main steam line outside, but close to, containment. The MSIVs are downstream from the Main Steam Safety Valves (MSSVs), atmospheric dump valves, and auxiliary feedwater pump turbine steam supplies to prevent their being isolated from the steam generators by MSIV closure.

Closing the MSIVs isolates each steam generator from the other, and isolates the turbine, Steam Bypass Control System, and other auxiliary steam supplies from the steam generators.

The LCO for TS 3.7.2 states that "Four MSIVs shall be OPERABLE" with the applicability "MODE 1, MODES 2, 3, and 4 except when all MSIVs are closed."

Condition C, "One or more MSIVs inoperable in MODE 2, 3, or 4" requires that the inoperable MSIV be closed within "4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />" and verified closed "Once per 7 days." The NUREG-1432 applicability for this LCO includes the bracketed words "[and deactivated]." The original PVNGS TS only required that an inoperable MSIV be maintained closed and did not specifically require that the MSIV be deactivated.

However, APS has determined that the same inconsistency described above for the MFIVs, applies to this LCO and proposes to add 'and deactivated" to the applicability.

This change corrects the inconsistency between the current applicability and the required action.

Therefore, this is considered an administrative change that corrects an inconsistency in TSs 3.7.2 and 3.7.3.

Technical Specification 3.8.1 Amendment 129 to the PVNGS Operating License revised the voltage and frequency limits in the SRs for TS 3.8.1, "AC Sources - Operating." As part of the change, a note was added to each of the affected SRs, except SR 3.8.1.2, stating that "The steady state voltage and frequency limits are analyzed values and have not been adjusted for instrument error." However, the voltage and frequency limits were also revised in SR 3.8.1.2. This change corrects this inconsistency by adding the note to SR 3.8.1.2.

Technical Specifications 3.8.4 and 3.8.6 APS has replaced the AT&T batteries with low specific gravity batteries in all three units.

This change removes the requirements and references to the AT&T batteries from the TS.

As part of the replacement of the AT&T batteries, PVNGS received a one-time deferral from the requirement to perform a performance discharge test on the Unit 1 AT&T batteries until startup from the ninth Unit 1 refueling outage. The AT&T batteries were replaced prior to startup from the ninth Unit I refueling outage. Therefore, the one-time deferral no longer applies and the note is being deleted.

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Since AT&T batteries are no longer installed at PVNGS, these requirements are no longer applicable and are being removed from TS.

Technical Specification 5.5.9 Tables 5.5.9-2 and 5.5.9-3 require NRC notification in accordance with 10 CFR 50.72 when the condition of the nuclear power plant, including its principal safety barriers, are seriously degraded (e.g., defective steam generator tubes). Prior to January 23, 2001, this requirement was in 10 CFR 50.72 (b)(2). A rule change was issued for 10 CFR 50.72 on January 23, 2001. As part of the rule change, the reporting requirement for this criteria was changed to an 8-hour non-emergency report in 10 CFR 50.72 (b)(3).

Therefore, this change corrects NRC notification requirements based on the January 23, 2001 rule change to 10 CFR 50.72 (65 FR 63786, 10/25/00).

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration Arizona Public Service (APS) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1.

Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed amendment includes following changes that are considered to be administrative and/or editorial changes:

The reporting requirement in License Condition 2.F (2.G in Unit 3) is adequately addressed by the requirements identified in 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors" and 10 CFR 50.73, "Licensee event report system." Since Condition 2.F (2.G in Unit 3) is adequately addressed by the requirements in 10 CFR 50.72 and 10 CFR 50.73, the Condition is not required. Therefore, this is considered an administrative change that eliminates regulatory requirements that are adequately addressed by the requirements in 10 CFR 50.72 and 10 CFR 50.73.

The changes to Technical Specifications (TS) 1.4 and 3.4.3 are editorial changes only. These changes maintain the format of the Technical Specifications and correct editorial errors in the Technical Specifications.

E2-11

The changes to Technical Specifications 2.1.1 and 3.3.1 remove requirements that are no longer applicable to the Palo Verde Nuclear Generating Station (PVNGS) units. As part of Amendment 133 to the PVNGS Operating License, the minimum DNBR was revised based on Unit operating cycle, '>1.30 (through operating cycle 10)" and "Ž1.34 (operating cycle 11 and later)." All three PVNGS units have completed operating cycle 10. Therefore, the reference to the minimum daparture from nucleate boiling ratio (DNBR) through operating cycle 10 (Ž1.30) is no longer required.

The changes to Technical Specification 3.1.10 correct an inconsistency between the Technical Specification limiting condition for operation (LCO) and Bases. The Bases for this specification states that "Even if an accident occurs during PHYSICS TESTS with one or more LCOs suspended, fuel damage criteria are preserved because the limits on power distribution and shutdown capability are maintained during PHYSICS TESTS." The limits on power distribution are maintained by TSs 3.2.1, "Linear Heat Rate (LHR)" and 3.2.4 "Departure from Nucleate Boiling Ratio (DNBR)." These changes ensure that shutdown capability is maintained during physics tests.

The changes to Technical Specifications Section 3.7.2, "Main Steam Isolation Valves (MSIVs)" and Section 3.7.3, "Main Feedwater Isolation Valves (MFIVs)" correct an inconsistency between the applicability and the required actions. The changes are consistent with the guidance in NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants." Therefore, this is considered an administrative change that corrects an inconsistency in the Technical Specifications.

The changes to Technical Specifications Section 3.8.1, "AC Sources -

Operating," correct an inconsistency in the surveillance requirements that were revised in Amendment 129 to the PVNGS Operating License. A note was not included with the change to one of the surveillance requirements. This change adds the note to the surveillance requirement.

Therefore, this is considered an administrative change that corrects an inconsistency in the Technical Specifications.

The changes to Technical Specifications Section 3.8.4, "DC Sources -

Operating" and Section 3.8.6, "Battery Cell Parameters" removes the requirements and references to the AT&T batteries. APS has replaced the AT&T batteries with low specific gravity batteries in all three units.

Therefore, this is considered an administrative change that removes unnecessary requirements and references.

E2-12

The changes to Technical Specifications Section 5.5.9, "Steam Generator (SG) Tube Surveillance Program," updates the requirement to notify the NRC based on the January 23, 2001 rule change to 10 CFR 50.72.

Therefore, this change corrects NRC notification requirements in Technical Specifications, based on the January 23, 2001 rule change to 10 CFR 50.72 (65 FR 63786, 10/25/00).

As discussed above the proposed amendment involves administrative and/or editorial changes only. The proposed amendment does not impact any accident initiators, analyzed events, or assumed mitigation of accident or transient events. The proposed changes do not involve the addition or removal of any equipment or any design changes to the facility. The proposed changes do not affect plant operations, any design function or an analysis that verifies the capability of structures, systems, and components (SSCs) of the plant. The proposed changes do not change any of the previously evaluated accidents in the updated final safety analysis report (UFSAR). The proposed changes do not affect SSCs, operating procedures, and administrative controls that have the function of preventing or mitigating any of these accidents.

Therefore, the proposed changes do not represent a significant increase in the probability or consequences of an accident previously evaluated.

2.

Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No As discussed in standard 1, the proposed amendment only involves administrative and/or editorial changes. No actual plant equipment or accident analysis will be affected by the proposed changes. The proposed changes will not change the design function or operation of any SSCs. The proposed changes will not result in any new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases. The proposed amendment does not impact any accident initiators, analyzed events, or assumed mitigation of accident or transient events.

Therefore, this proposed change does not create the possibility of an accident of a different kind than previously evaluated.

E2-13

3.

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

Response: No As discussed in standard 1, the proposed amendment only involves administrative and/or editorial changes. Margin of safety is associated with confidence in the ability of the fission product barriers (i.e., fuel and fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. This request involves administrative and/or editorial changes only. No actual plant equipment or accident analysis will be affected by the proposed changes.

Additionally, the proposed changes will not relax any criteria used to establish safety limits, will not relax any safety system settings, or will not relax the bases for any limiting conditions for operation.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

==

Conclusion:==

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

5.2 Applicable Regulatorv Requirements/Criteria Operating License Condition 2.F (2.G in Unit 3) 10 CFR 50.72: "Immediate notification requirements for operating nuclear power reactors." This regulatory requirement contains general requirements (section (a)), requirements for reporting non-emergency events (section (b)), and requirements for providing followup notification (section c)).

10 CFR 50.73(a) Reportable events. (1) The holder of an operating license for a nuclear power plant (licensee) shall submit a Licensee Event Report (LER) for any event of the type described in this paragraph within 60 days after the discovery of the event. In the case of an invalid actuation reported under § 50.73(a)(2)(iv), other than actuation of the reactor protection system (RPS) when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER. Unless otherwise specified in this section, the licensee shall report an event if it occurred within three years of the E2-14

date of discovery regardless of the plant mode or power level, and regardless of the significance of the structure, system, or component that initiated the event.

The proposed deletion of Operating License Condition 2.F (2.G in Unit 3) will reduce unnecessary regulatory burden, allowing APS to follow the requirements of 10 CFR 50.72 and 10 CFR 50.73.

Changes to Technical Specifications The proposed changes to the Technical Specifications are administrative and/or editorial and do not affect any regulatory requirements/criteria.

Conclusion Therefore, based on the considerations discussed above:

1) There is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner;
2) Such activities will be conducted in compliance with the Commission's regulations; and
3) Issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

APS has evaluated the proposed amendment and determined the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendments meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental impact statement or environmental assessment of the proposed amendment is not required.

7.0 PRECEDENT The NRC issued License Amendment 155 for Fermi 2 on May 16, 2003, License Amendment 103 for Comanche Peak Steam Electric Station, Units 1 and 2 on May 15, 2003, License Amendment 141 for Wolf Creek Generating Station on September 24, 2001, and License Amendments 129 and 118 for South Texas Project, Units 1 and 2 on E2-15

August 16, 2001. These approved License Amendments are similar to the deletion of License Condition 2.F (2.G in Unit 3) in this License Amendment Request.

8.0 REFERENCES

1. 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors"
2. 10 CFR 50.73, "Licensee event report system"
3. NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants," Rev. 3, June 2004
4. NRC letter dated October 4, 2000, to Gregg R. Overbeck, Arizona Public Service Company, "Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments on Diesel Generator Steady-State Voltage and Frequency (TAC Nos. MA9214, MA9215, and MA9216)" Amendment No. 129
5. NRC letter dated March 28, 2001, to Gregg R. Overbeck, Arizona Public Service Company, "Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments to Changing the Minimum Departure of the Nucleate Boiling Ratio (TAC Nos. MB0745, MB0746, and MB0747)" Amendment No. 133
6. NRC letter dated May 16, 2003, to William T. O'Connor, Jr., Detroit Edison Company, "Fermi 2 - Issuance of Amendment RE: Deletion of Three Obsolete License Conditions and the Reporting Requirements in the Operating License (TAC No. MB5170)" Amendment No. 155
7. NRC letter dated May 15, 2003, to C. Lance Terry., TXU Energy, 'Comanche Peak Steam Electric Station (CPSES), Units 1 and 2 Issuance of Amendments RE: Deletion of Unnecessary License Conditions and Reporting Requirements (TAC Nos. MB5770 and MB5771)" Amendment No. 103
8. NRC letter dated September 24, 2001, to Otto L. Maynard, Wolf Creek Nuclear Operating Corporation, "Wolf Creek Generating Station - Issuance of Amendment Regarding Deletion of License Conditions and Revision to Steam Generator Tube Inspection Table 5.5.9-2 (TAC No. MB1611)" Amendment No.

141

9. NRC letter dated August 16, 2001, to William T. Cottle, STP Nuclear Operating Company, 'South Texas Project, Units 1 and 2 - Issuance of Amendments on Reporting Requirements (TAC Nos. MB1057 and MB1058)" Amendment Nos.

129 and 118 E2-16 Proposed Operating License and Technical Specification Changes (mark-up)

F.

-Except as oto rwise provided i he Technical Speiications or the lEnvironmepfal Protection Plap APS shall report 3tyviolationofte requirem ts contained in ction 2.C of this Ii nse in the followi manner:

Initial tification shall b ade within 24 ho s in accordance h the provi ons of 10 CFR 5.72 with written foil

-up within 30 da in ac rdance with the ocedures describ in 10 CFR 50.73 ), (c) and (e);

G.

The licenses shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims; and H.

This license is effective as of the date of issuance and shall expire at midnight on June 01, 2025.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Harold R. Denton, Director Office of Nuclear Reactor Regulation

Enclosures:

1. Attachment 1 - [Requirements for Initial Mode I Entry] - Deleted
2. Attachment 2 - [Operating Staff Experience Requirements] - Deleted
3. Attachment 3 - [Emergency Response Capabilities] - Deleted
4. Appendix A -

Technical Specifications

5. Appendix B -

Environmental Protection Plan

6. Appendix C -

Antitrust Conditions

7. Appendix D - [Additional Conditions] - Deleted Date of Issuance: June 1, 1985 Amendment No. 44, 428,147

ViZ L.- (9)

Additional Conditions Deleted D.

(1)

APS has previously been granted an exemption from Paragraph IlI.D.2(b)(ii) of Appendix J to 10 CFR Part 50. This exemption was previously granted in Facility Operating License NPF-46 pursuant to 10 CFR 50.12.

(2)

Deleted With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E.

The licensees shall fully implement and maintain in effect all provisions of the Commission-approved physical security, 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 ofl 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: uPalo Verde Nuclear Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and Independent Spent Fuel Storage Installation Security Program Revision 0," submitted by letter dated October 22, 2004.

F.

S _xcept as otherfse provided in theTechnical Sp ifications or the

nvironmental rotection Plan,S shall report ny violations oft equirement contained in Sec on 2.C of this Hense in the followi manner:

nitial notif ation shall be made within 24 ho rs to the NRC Ope tions Center ia the ergency Notific on System wit written follow-up w in 30 days in ccor nce with the prog dures describ in 10 CFR 50.73, c) and e; TH13DOCU~ff AS BEN MEWOAmendment No. 469,4+60, +28l ANTI DOETUMN TO N CONTAIN Revised by letter dated October 28, 2004 SFEgUADS WoATION SO AMIN DATh1

  1. 1

&(ni 7 3 O0L-I F.

APS shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety analysis Report for the facility, as supplemented and amended, and as approved in the SER through Supplement 11, subject to the following provision:

APS may make changes to the approved fire protection program without approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G.

xcept otherwise p vided In th echnical Vecifications r the Enviro fnental Proteeion Plan, A S shall rept any violatics of the requiements cont ned in Sect n 2.C of thi icense In th/following m ner:

lnit~I notificationhall be ma within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NKC Operation Center vf the Emergency Notificati n System, Oh written foylw-up within days in ccordance h the proce ures described in 10 CF 50.73(b), (c)/nd (e);

H.

The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims; and I.

This license is effective as of the date of issuance and shall expire at midnight on November 25, 2027.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:

1. [Requirements for Initial Mode 1 Entry] - Deleted
2. Appendix A -

Technical Specifications

3. Appendix B -

Environmental Protection Plan

4. Appendix C -

Antitrust Conditions

5. Appendix D -

[Additional Conditions] - Deleted Date of Issuance: November 25, 1987 THIS DOCUENT HA BEEN REVIEWED AND DETERNIED TO NOT CONTAIN AEQUARDS INfORMATION SOADMIN Amendment No. B3, 7, 46, 447 Revised by letter dated October 28, 2004

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO.

An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0.

Surveillance Requirement (SR) Applicability.

The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.

Situations where a Surveillance could be required (i.e.. its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e.. the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied. SR 3.0.4 imposes no restriction.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified.

In these examples, the Applicability of the LCO (LCO not shown) is MODES 1. 2.

and 3.

PALO VERDE UNITS 1.2.3 1.4-1 AMENDMENT NO. 117

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2. Departure from Nucleate Boiling Ratio (DNBR) shall be maintaine s ol

< g

.3 Xhrough opd ating cy/ e I0 2.1.1.2 In MODES 1 and 2. the peak fuel centerline temperature shall be maintained < 50800F (decreasing by 581F per 10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A).

2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1. 2. 3. 4. and 5, the RCS pressure shall be maintained at < 2750 psia.

2.2 SL Violations 2.2.1 If SL 2.1.1.1 or SL 2.1.1.2 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 2.2.2.2 In MODE 3. 4. or 5. restore compliance within 5 minutes.

2.2.3 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center. in accordance with 10 CFR 50.72.

2.2.4 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Director, Operations and the Senior' Vice President, Nuclear.

(continued)

PALO VERDE UNITS 1,2.3 2.0-1 AMENDMENT NO. 445 146

STE - MODES 1 and 2 3.1.10 3.1 REACTIVITY CONTROL SYSTEMS 3.1.10 Special Test Exceptions (STE) - MODES 1 and 2 LCO 3.1.10 During performance of PHYSICS TESTS. the requirements of:

LCO 3.1.4.

LCO 3.1.5, LCO 3.1.6.

LCO 3.1.7.

LCO 3.1.8.

"Moderator Temperature Coefficient (MTC)":

"Control Element Assembly (CEA) Alignment":

"Shutdown Control Element Assembly (CEA)

Insertion Limits":

"Regulating Control Element Assembly (CEA)

Insertion Limits":

"Part Length or Part Strength CEA Insertion Limits":

"Planar Radial Peaking Factors (Fxy)":

"AZIMUTHAL POWER TILT (Tq)":

"AXIAL SHAPE INDEX (ASI)": and "Control Element Assembly Calculators (CEACs)"

I LCO LCO LCO LCO 3.2.2.

3.2.3, 3.2.5.

3.3.3.

1: / 0 -<1 El-may be suspended l~ovided TIFIAMAL POWER is Restricted to Cmne TeJt power pl6teau, whicY shall not exceed 85% RTP. J APPLICABILITY:

MODES 1 and 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Test power plateau A.1 Reduce THERMAL POWER 15 minutes exceeded.

to less than or equal to the test power plateau.

B. Required Action and B.1 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion TESTS.

Time not met.

PALO'VERDE UNITS 1.2,3 3.1.10-1 AMENDMENT NO. 44y, 152

Insert Page Technical Specification 3.1.10 LCO Insert provided:

a.

THERMAL POWER is restricted to the test power plateau, which shall not exceed 85% RTP: and

b.

Shutdown reactivity equivalent to at least the highest estimated CEA worth (of those CEAs actually withdrawn) is available for trip insertion.

INSERT PAGE 3.1.10-1

STE - MODES 1 and 2 3.1.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.10.1 Verify THERMAL POWER equal to or less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the test power plateau..

c-r PALO VERDE UNITS 1,2.3 3.1.10-2 AMENDMENT NO. 117

Technical Specification 3.1.10 Surveillance Requirements Insert SR 3.1.10.2 Verify that the position of each CEA not fully 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> inserted is within the acceptance criteria for available negative reactivity addition.

INSERT PAGE 3.1.10-2

RPS Instrumentation - Operating (Before CPC Upgrade) 3.3.1 Table 3.3.1-1 (page 3 of 3)

Reactor Protective System Instrumentation I

APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIREMENTS ALLOWABLE VALUE

14.

Local Power Density - High(b) 1.2 SR 3.3.1.1 s 21.0 kW/ft SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13

15.

Departure From Nuclpte Boiling 1.2 SR 3.3.1.1 1.3/(througV -I Ratio (DNBR) - Low SR 3.1.2 o

1r3ing cy le IOU SR 3.3.1.3 SR 3.3.1.41 SR 3.3.1.5 1.4o ai i l

SR 3.3.1.7a r

SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11.

SR 3.3.1.12 SR 3.3.1.13 (b) Trip may be bypassed when logarithmic power Is < 1E-4% NRTP.

when logarithmic power is 2 1E-4% NRTP.

Bypass shall be automatically removed PALO VERDE UNITS 1,2,3 3.3.1-10 AMENDMENT NO. 4-33, 150

RPS Instrumentation - Operating (After CPC Upgrade) 3.3.1 Table 3.3.1-1 (page 3 of 3)

Reactor Protective System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIREMENTS ALLOWABLE VALUE

14.

Local Power Density - High(b) 1.2 SR 3.3.1.1 s 21.0 kW/ft SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13

15.

Departure From Nucigpte Boiling 1.2 SR 3.3.1.1 l

- 1 hro Ratio (DNBR)

L L

SR 3.3.1 lIopeypting cy 4e 10))

SR 3.3.1.3 (

SR 3.3.1.5 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13 (b) Trip may be bypassed when logarithmic power is < 1E-4S NRTP.

when logarithmic power is 2 1E-4% NRTP.

Bypass shall be automatically removed PALO VERDE UNITS 1.2.3 3.3. 1-19 AMENDMENT NO.

150

RCS P/T Limits 3.4.3 TABLE 3.4.3-1 Maximum Allowable Heatup and Cooldown Rates

<8 Effective Full Power Years Heatup TcX (°F)

Rate (°F/HR)

< 128°F 20°F/HR 128°F - 180°F 30°F/HR 1810 - 230°F 50°F/HR

> 230°F 75°F/HR Cooldown TCX CIF)

Rate (°F/HR)

< 93°F See Figure 3.4.3-3 94°F - 114°F 10°F/HR 115OF - 148°F 20°F/HR

> 148°F 100°F/HR 8-32 Effective Full Power Years Heatup TCX (OF)

Rate (°F/HR)

< 116OF 10°F/HR 117°F - 150OF 20°F/HR 1510 - 199°F 30°F/HR 200°F - 246°F 50°F/HR

> 246°F 750F4 Cooldown TCX (°F)

Rate (°F/HR)

< 108°F See Figure 3.4.3-4 1090 - 126°F 10°F/HR 127°F - 147°F 20°F/HR 148°F - 162°F 40°F/HR

>162°F 100°F/HR x Indicated Cold Leg Temperature W

PALO VERDE UNITS 1,2.3 3.4.3-3 AMENDMENT NO.

117

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 APPLICABILITY:

Four MSIVs shall be OPERABLE.

closed.

MODE 1.

MODES 2. 3. and 4 except when all MSIVs are ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> MODE 1.

OPERABLE status.

B. Required Action and B.1 --

-Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion Time of Condition A not met.

C. --------- NOTE--------- C.1 Close MSIV.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Separate Condition entry is allowed for AND each MSIV.

C.2 Verify MSIV is Once per 7 days closed.

One or more MSIVs inoperable in MODE 2.

3. or 4.

D. Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition C AND not met.

D.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> PALO VERDE UNITS 1.2.3 3.7.2-1 AMENDMENT NO. 117

MFIVs 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs)

LCO 3.7.3 APPLICABILITY:

Four economizer MFIVs and four downcomer MFIVs shall be OPERABLE.

MODES 1, 2. 3, and 4 except when MFIV is closed or isoli by a closed power operated valve. _

ACTIONS NOTE------------------------------------

Separate Condition entry is allowed for each penetration flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFIVs A.1 Close or isolate 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.

inoperable MFIV.

AND A.2 Verify inoperable Once per 7 days MFIV is closed or isolated.

B. Two valves in the B.1 Isolate affected flow 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> same flow path path.

inoperable.

AND B.2 Verify inoperable Once per 7 days MFIV is closed or isolated.

(continued PALO VERDE UNITS 1.2,3 3.7.3-1 AMENDMENT NO.

117

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker'alignment and 7 days indicated power availability for each required offsite circuit.

  • SR 3.8.1.2

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

1.

Performance of SR 3.8.1.7 satisfies

.this SR.

2.

All DG starts may be preceded by an

  • engine prelube period and followed by a warmup period prior to loading.
  • 3. -A modified DG start involving idling and gradual acceleration to.

synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time.

.voltage. and frequency tolerances of.SR 3.8.1.7 must be met.

7 Verify each DG starts from standby.

31 days condition and achieves steady state voltage 2 4000 V and < 4377.2 V. and frequency 2 59.7 Hz and < 60.7 Hz.

I, analyzed values and have not been adjusted for instrument error.

(continued)

PALO VERDE UNITS 1.2.3 3.8.1-6 AMENDMENT NO. Aid7. 129

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltaqe is Ž 129 V 7 days on float charqef(lowApecific graity ce Is)

Ž 2 131 V 0 float char e (AT&T).J SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.

OR Verify battery connection resistance is

< 150E-6 ohms for inter-cell connections.

< 150E-6 ohms for inter-rack connections.

< 150E-6 ohms for inter-tier connections.

and < 150E-6 ohms for terminal connections.

SR 3.8.4.3 Verify battery cells, cell plates. and 18 months racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.

SR 3.8.4.4 Remove visible terminal corrosion and 18 months verify battery cell to cell and terminal connections are clean, and are coated with anti-corrosion material.

SR 3.8.4.5 Verify battery connection resistance is 18 months

< 150E-6 ohms for inter-cell connections.

< 150E-6 ohms for inter-rack connections.

< 150E-6 ohms for inter-tier connections.

and < 150E-6 ohms for terminal connections.

(continued)

PALO VERDE UNITS 1.2,3 3.8.4-2 AMENDMENT NO. 117

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.8

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

This Surveillance shall not be performed in MODE 1, 2. 3. or 4.

Verify battery capacity is 2 80% (Ao-w-)

ospeor v 9 AT

% AA_

of the maUcturerOs7ratng when subjected to a performance discharge test or a modified performance discharge test.0 60 months AND 12 months when battery shows degradation or has reached 85%

of the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity 2 100% of manufacturer's rating I

i* The equirement to p rform SR 3.8.4/.8 for the Unit batteries A. B, andC is waived unt/l entry into MODE 4 coming out f the ninth I

refueling outage f r Unit 1 (1R091.

PALO VERDE UNIT 1 AMENDMENT NO. 121 PALO VERDE UNITS 2.3 3.8.4-4 AMENDMENT NO. 117

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 offs) (Low pecific ravitykells)

Battery Surveillance Requirements CATEGORY A:

CATEGORY C:

LIMITS FOR EACH CATEGORY B:

ALLOWABLE LIMITS DESIGNATED PILOT LIMITS FOR EACH FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte Level

> Minimum level

> Minimum level Above top of indication mark, indication mark.

plates, and not and < V inch and < Y, inch overflowing above maximum above maximum level indication level indication mark(a) mark(a)

Float Voltage 2 2.13 V 2 2.13 V(d)

> 2.07 V Specific 2 1.200 2 1.195 Not more than Gravity(b)(c) 0.020 below average connected cells AND AND Average of all Average of all connected cells connected cells 2 1.205

> 1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature and level.

Level correction is not required, however, when battery charging is < 2 amps when on float charge.

(c) A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements, specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.

(d) Corrected for average electrolyte temperature.

PALO VERDE UNITS 1.2.3 3.8.6-4 AMENDMENT NO. 117

X3,V6ed LLS27-D Battery Cell Parameters 3.8.

Table 3.8.6-1 (page 2 of 2) (AT&T)

Battery Surveillance Requirements CATEGORY A:

CATEGO Y C:

LIMITS FOR EACH CATEGORY B:

ALLOWAB LIMITS DESIGNATED PILOT LIMITS FOR EACH FO EACH ETER CELL CONNECTED CELL CON CTED CELL Electrolyt Level

> Minimum level

> Minimum level Ab ye top of indication mark, indication mark, ates, and not and < 'a inch and < '4 inch verflowing above maximum.

above maximum level indication level indicatio mark(a) mark(a)

Float Voltage 2.18 V 2 2.18 V(

> 2.14 V Specific 2 1.29 2 1. 80 Not more than Gravi ty(b) (c) 0.020 below average connected cells AND AND Average of all Average of all connected cells connected cells

> 1.290 2 1.280 (a) It is acceptable for the electrolyte 1 el to temporarily increase above the specified maximum ring equalizing harges provided it is not overflowing.

(b) Corrected for elect olyte temperature and l el.

Level correction is not required, how er. when battery charging

< 2 amps when on float charge.

(c) A battery char ng current of < 2 amps when on fl at charge is acceptable fo meeting specific gravity limits fol wing a battery recharge. fo a maximum of 7 days.

When charging c rent is used to satisfy spe ific gravity requirements, specific gravi of each connected ell shall be measured prior to expiration o the 7 day allowanc (d) Correc ed for average electrolyte temperature.

PALO V E UNITS 1.2.3 3.8.6-5 AMENDME NO.

117

TABLE 5.5.9-2 GENERATOR TUBE INSPECTION STEAM I

1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N.A.

N.A.

N.A.

N.A.

S Tubes per S.G STbsprSGC-1 None N.A.

N.A.

C-2 Plug or repair defective tubes and inspect C-2 Plug or repair C-1 None additional 2S tubes in defective tubes and this S.G.

inspect additional C-2 Plug or repair 4S tubes In this defective tubes S.G.

C-3 Perform action for C-3 result of first sample C-3 Perform action N.A.

N.A.

for C-3 result of l

first samnle C-3 i

Sp G, plug or repai r All other S.G.s None N.A.

N.A.

defective tubes and are C-1 ins ect 2S tubes in each other S.G.

Some S.G.s C-2.

Perform action N.A.

N.A.

but no for C-2 result of Notification to NRC additional S.G.

second sample pursuant to 10 CFR 50.72 are C-3 (b)(i7)

Additional S.G.

Inspect all tubes N.A.

N.A.

is C-3 in each S.G. and plug or repair defective tubes Notification to (

NRC pursuant to l_

10 CFR 50.72 (b)

S = 3 -

% Where N is the number of steam generators in the unit, and n is the number of steam generators n

inspected during an inspection.

PAO ERE NIS

.23

.515AMNDEN N. -17~12 PALO VERDE UNITS 1.2.3 5.5-15 AMENDMENT NO. Age7 120

TABLE 5.5.9-3 STEAM GENERATOR SLEEVE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION Sample Size Result Action Required Result Action Required A minimum of C-1 None l

_N.A.

N.A.

20% of the sleeves per C-2 Plug tubes containing defective sleeves and inspect all remaining C-2 Plug tubes containing defective sleeves installed sleeves in this S.G.

C-3 Perform action for C-3 result of first sample C-3 Inspect all installed sleeves in Other S.G. is None this S.G.. plug tubes containing C-1 defective sleeves and inspect 100 of the installed sleeves in the Other S.G. is Plug tubes containing defective sleeves other S.G.

C-2 Notification to NRC pursuant to l

10 CFR 50.72 (b Other S.G. is Inspect all sleeves in each S.G. and plug tubes C-3 containing defective sleeves.

Notification to NRC pursuant to 10 CFR 50.72(b) e)

PALOVERE UITS

,2.

5.-16AMENMEN NO 12 PALO VERDE UNITS 1,2.3 5.5-16 AMENDMENT NO.

120 Proposed Technical Specification Changes (retyped)

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO.

An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0.

Surveillance Requirement (SR) Applicability.

The "specified Frequency" consists of the requirements of the Frequency column of each SR. as well as certain Notes in the Surveillance column that modify performance requirements.

Situations where a Surveillance could be required (i.e.. its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples. the Applicability of the LCO (LCO not shown) is MODES 1, 2.

and 3.

(continued)

I PALO VERDE UNITS 1.2.3 1.4-1 AMENDMENT NO. 4--7

SLs 2.0 2.0 SLs 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2. Departure from Nucleate Boiling Ratio (DNBR) shall be maintained at 2 1.34.

2.1.1.2 In MODES 1 and 2. the peak fuel centerline temperature shall be maintained < 50800F (decreasing by 580F per 10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A).

2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1. 2. 3, 4. and 5. the RCS pressure shall be maintained at < 2750 psia.

2.2 SL Violations 2.2.1 If SL 2.1.1.1 or SL 2.1.1.2 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2 If SL 2.1.2 is violated:

2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.2.2.2 In MODE 3. 4. or 5, restore compliance within 5 minutes.

2.2.3 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. notify the NRC Operations Center. in accordance with 10 CFR 50.72.

2.2.4 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Director, Operations and the Senior Vice President. Nuclear.

(continued)

PALO VERDE UNITS 1,2.3 2.0-1 AMENDMENT NO. 446

STE - MODES 1 and 2 3.1.10 3.1 REACTIVITY CONTROL SYSTEMS 3.1.10 Special Test Exceptions (STE) - MODES 1 and 2 LCO 3.1.10 During performance of PHYSICS TESTS, the requirements of:

LCO 3.1.4.

LCO 3.1.5.

LCO 3.1.6.

LCO 3.1.7.

LCO 3.1.8.

"Moderator Temperature Coefficient (MTC)";

"Control Element Assembly (CEA) Alignment";

"Shutdown Control Element Assembly (CEA)

Insertion Limits":

"Regulating Control Element Assembly (CEA)

Insertion Limits";

"Part Length or Part Strength CEA Insertion Limits";

"Planar Radial Peaking Factors (Fxy)";

"AZIMUTHAL POWER TILT (Tq)":

"AXIAL SHAPE INDEX (ASI)": and "Control Element Assembly Calculators (CEACs)"

LCO LCO LCO LCO 3.2.2, 3.2.3.

3.2.5.

3.3.3.

may be suspended, provided:

a. THERMAL POWER is restricted to the test power plateau, which shall not exceed 85% RTP: and
b.

Shutdown reactivity equivalent to at least the highest estimated CEA worth (of those CEAs actually withdrawn) is available for trip insertion.

APPLICABILITY:

MODES 1 and 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Test power plateau A.1 Reduce THERMAL POWER 15 minutes exceeded.

to less than or equal to the test power plateau.

B. Required Action and B.1 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion TESTS.

Time not met.

PALO VERDE UNITS 1.2.3 3.1.10-1 AMENDMENT NO. 4,59

STE - MODES 1 and 2 3.1.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.10.1 Verify THERMAL POWER equal to or less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the test power plateau.

SR 3.1.10.2 Verify that the position of each CEA not 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fully inserted is within the acceptance criteria for available negative reactivity addition.

PALO VERDE UNITS 1.2,3 3.1.10-2 AMENDMENT NO. an1y

RPS Instrumentation - Operating (Before CPC Upgrade) 3.3.1 Table 3.3.1-1 (page 3 of 3)

Reactor Protective System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIREMENTS ALLOWABLE VALUE

14.

Local Power Density - High(b) 1.2 SR 3.3.1.1

15.

Departure From Nucleate Boiling 1.2 SR 3.3.1.1 2 1.34 Ratio (DNBR) - Low(D)

SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13 (b) Trip may be bypassed when logarithmic power is < 1E-4% NRTP.

when logarithmic power is 2 1E-4% NRTP.

Bypass shall be automatically removed PALO VERDE UNITS 1,2,3 3.3.1-10 AMENDMENT NO. 1504.

RPS Instrumentation - Operating (After CPC Upgrade) 3.3.1 Table 3.3.1-1 (page 3 of 3)

Reactor Protective System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE FUNCTION CONDITIONS REQUIREMENTS ALLOWABLE VALUE

14.

Local Power Density - High(b) 1.2 SR 3.3.1.1 s 21.0 kW/ft SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13

15.

Departure From Nucjg~te Boiling 1.2 SR 3.3.1.1 2 1.34 Ratio (DNBR) - Low SR 3.3.1.2 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.7 SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13 (b) Trip may be bypassed when logarithmic power is < 1E-4% NRTP.

when logarithmic power is 2 1E-4% NRTP.

Bypass shall be automatically removed PALO VERDE UNITS 1,2.3 3.3. 1-19 AMENDMENT NO. Gl

RCS P/T Limits 3.4.3 TABLE 3.4.3-1 Maximum Allowable Heatup and Cooldown Rates

<8 Effective Full Power Years Heatup TCx (OF)

Rate (°F/HR)

< 128°F 20°F/HR 128°F - 180°F 30°F/HR 1810 - 230°F 50°F/HR

> 230°F 75°F/HR Cooldown Tcx (OF)

Rate (°F/HR)

< 93°F See Figure 3.4.3-3 94°F - 114°F 10°F/HR 115°F - 148°F 20°F/HR

> 148°F 100°F/HR 8-32 Effective Full Power Years Heatup Tcx (OF)

Rate (°F/HR)

< 116°F 10°F/HR 117°F - 150°F 20°F/HR 1510 - 199°F 30°F/HR 200°F - 246°F 50°F/HR

> 246°F 75°F/HR Cooldown Tcx (OF)

Rate (°F/HR)

< 108°F See Figure 3.4.3-4 1090 - 126°F 10°F/HR 127°F - 147°F 20°F/HR 148°F - 162°F 40°F/HR

>162°F 100°F/HR I

x Indicated Cold Leg Temperature PALO VERDE UNITS 1.2.3 3.4.3-3 AMENDMENT NO. 4-4:,z

MSIVs 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs)

LCO 3.7.2 Four MSIVs shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2. 3. and deactivated.

4 except when all MSIVs are closed and ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in A.1 Restore MSIV to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> MODE 1.

OPERABLE status.

B. Required Action and B.1 Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion Time of Condition A not met.

C. --------- NOTE---------

C.1 Close MSIV.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Separate Condition entry is allowed for AND each MSIV.

C.2 Verify MSIV is Once per 7 days closed.

One or more MSIVs inoperable in MODE 2.

3. or 4.

D. Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition C AND not met.

D.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> PALO VERDE UNITS 1,2,3 3.7.2-1 AMENDMENT NO. 44 MFIVs 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs)

LCO 3.7.3 APPLICABILITY:

ACTIONS Four economizer MFIVs and four downcomer MFIVs shall be OPERABLE.

MODES 1. 2. 3. and 4 except when MFIV is closed and deactivated or isolated by a closed and deactivated power operated valve.

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

Separate Condition entry is allowed for each penetration flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFIVs A.1 Close or isolate 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.

inoperable MFIV.

AND A.2 Verify inoperable Once per 7 days MFIV is closed or isolated.

B. Two valves in the B.1 Isolate affected flow 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> same flow path path.

inoperable.

AND B.2 Verify inoperable Once per 7 days MFIV is closed or isolated.

(continued)

PALO VERDE UNITS 1,2,3 3.7.3-1 AMENDMENT NO. 4-47

AC Sources -

Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and 7 days indicated power availability for each required offsite circuit.

SR 3.8.1.2

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

1.

Performance of SR 3.8.1.7 satisfies this SR.

2.

All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

3.

A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time.

voltage, and frequency tolerances of SR 3.8.1.7 must be met.

4.

The steady state voltage and frequency limits are analyzed values and have not been adjusted for instrument error.

Verify each DG starts from standby 31 days condition and achieves steady state voltage 2 4000 V and

  • 4377.2 V. and frequency 2 59.7 Hz and < 60.7 Hz.

(continued)

PALO VERDE UNITS 1.2,3 3.8.1-6 AMENDMENT NO. 12-9.

DC Sources - Operating 3.8.4 I

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 2 129 V 7 days on float charge.

SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.

OR Verify battery connection resistance is

< 150E-6 ohms for inter-cell connections.

< 150E-6 ohms for inter-rack connections.

< 150E-6 ohms for inter-tier connections.

and < 150E-6 ohms for terminal connections.

SR 3.8.4.3 Verify battery cells. cell plates. and 18 months racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.

SR 3.8.4.4 Remove visible terminal corrosion and 18 months verify battery cell to cell and terminal connections are clean, and are coated with anti-corrosion material.

SR 3.8.4.5 Verify battery connection resistance is 18 months

< 150E-6 ohms for inter-cell connections.

< 150E-6 ohms for inter-rack connections.

< 150E-6 ohms for inter-tier connections.

and < 150E-6 ohms for terminal connections.

(continued)

PALO VERDE UNITS 1.2,3 3.8.4-2 AMENDMENT NO. 4-1 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.8 NOTE--------------------

This Surveillance shall not be performed in MODE 1. 2. 3, or 4.

Verify battery capacity is 2 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

60 months AND 12 months when battery shows degradation or has reached 85%

of the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity 2 100% of manufacturer's rating I

I PALO VERDE UNIT 1.2.3 3.8.4-4 AMENDMENT NO. 24

Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Surveillance Requirements I

CATEGORY A:

CATEGORY C:

LIMITS FOR EACH CATEGORY B:

ALLOWABLE LIMITS DESIGNATED PILOT LIMITS FOR EACH FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte Level

> Minimum level

> Minimum level Above top of indication mark, indication mark, plates, and not and < it inch and < 't inch overflowing above maximum above maximum level indication level indication mark(a) mark(a)

Float Voltage 2 2.13 V

> 2.13 V(d)

> 2.07 V Specific 2 1.200 2 1.195 Not more than Gravity(b)(c) 0.020 below average connected cells AND AND Average of all Average of all connected cells connected cells

> 1.205

> 1.195 (a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum during equalizing charges provided it is not overflowing.

(b) Corrected for not required.

charge.

electrolyte temperature and level.

Level correction is however, when battery charging is < 2 amps when on float (c) A battery charging current of < 2 amps when on float charge is acceptable for meeting specific gravity limits following a battery recharge, for a maximum of 7 days. When charging current is used to satisfy specific gravity requirements. specific gravity of each connected cell shall be measured prior to expiration of the 7 day allowance.

(d) Corrected for average electrolyte temperature.

PALO VERDE UNITS 1.2.3 3.8.6-4 AMENDMENT NO. 447-

TABLE 5.5.9-2 GFNFRATOR TURE TNSPFCTTON STEAM 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N.A.

N.A.

N.A.

N.A.

S C-1 None N.A.

N.A.

C-2 Plug or repair defective tubes and inspect C-2 Plug or repair C-1 None additional 2S tubes in defective tubes and this S.G.

inspect additional C-2 Plug or repair 4S tubes in this defective tubes S.G.

C-3 Perform action for C-3 result of l_

first sample C-3 Perform action N.A.

N.A.

for C-3 result of I_

first samole C-3 iscG.t plug or repai r All other S.G.s None N.A.

N.A.

defective tubes and are C-1 inspect 2S tubes in each other S.G.

Some S.G.s C-2 Perform action N.A.

N.A.

but no for C-2 result of Notification to NRC additional S.G.

second sample pursuant to 10 CFR 50.72 are C-3 (b)(3)

Additional S.G.

Inspect all tubes N.A.

N.A.

is C-3 in each S.G. and plug or repair defective tubes.

Notification to NRC pursuant to l_

10 CFR 50.72 (b)(3)

S = 3 N 9 Where N is the number of steam generators in the unit, and n is the number of steam generators n

inspected during an inspection.

I I

PALO VERDE UNITS 1.2.3 5.5-15 AMENDMENT NO. 424

TABLE 5.5.9-3 STEAM GENERATOR SLEEVE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION Sample Size Result Action Required Result Action Required A minimum of C-1 None N.A.

N.A.

20% of the sleeves per C-1 None S.G.

C-2 Plug tubes containing defective sleeves and inspect all remaining C-2 Plug tubes containing defective sleeves installed sleeves in this S.G.

C-3 Perform action for C-3 result of first sample C-3 Inspect all installed sleeves in Other S.G. is None this S.G.. plug tubes containing C-1 defective sleeves and inspect 100 of the installed sleeves in the Other S.G. is Plug tubes containing defective sleeves other S.G.

C-2 Notification to NRC pursuant to 10 CFR 50.72 (b)(3)

Other S.G. is Inspect all sleeves in each S.G. and plug tubes C-3 containing defective sleeves.

Notification to NRC pursuant to 10 CFR 50.72(b)(3)

I I

PALO VERDE UNITS 1.2.3 5.5-16 AMENDMENT NO. 4-29 PALO VERDE UNITS 1.2.3 5.5-16 AMENDMENT NO. 4-29 Changes to Technical Specification Bases Pages (For Information Only)

Reactor Core SLs B 2.1.1 BASES APPLICABLE

h.

Log Power Level - High trip:

SAFETY ANALYSES (continued)

i.

Reactor Coolant Flow -

Low trip; and

j.

Steam Generator Safety Valves.

The limitation that the average enthalpy in the hot leg be less than or equal to the enthalpy of saturated liquid also ensures that the AT measured by instrumentation used in the protection system design as a measure of the core power is proportional to core power.

The SL represents a design requirement for establishing the protection system trip setpoints identified previously.

LCO 3.2.1. "Linear Heat Rate (LHR)," and LCO 3.2.4.

"Departure From Nucleate Boiling Ratio (DNBR)." or the assumed initial conditions of the safety analyses (as indicated in the UFSAR, Ref. 2) provide more restrictive limits to ensure that the SLs are not exceeded.

SAFETY LIMITS SL 2.1.1.1 and SL 2.1.1.2 ensure that the minimum DNBR is not less than the safety analyses limit and that fuel centerline temperature remains below melting.

The minimum value of the DNBR during normal operation and design basis AO0s is limited to ths va w

1.34 oroefatin c esT1 ad lat r, based on a statistical com nation cl CE-1 CHF correlation and engineering factor uncertainties, and is established as an SL.

Additional factors such as rod bow and spacer grid size and placement will determine the limiting safety system settings required to ensure that the SL is maintained. Maintaining the dynamically adjusted peak LHR to < 21 kW/ft or peak fuel centerline temperature < 50800F (decreasing by 580F per 10.000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A). ensures that fuel centerline melt will not occur during normal operating conditions or design AO0s.

The design melting point of new fuel with no burnable poison is 50800F. The melting point is adjusted downward from this temperature depending on the amount of burnup and amount and type of burnable poison in the fuel.

The 580F per 10.000 MWD/MTU adjustment for burnup was accepted by the NRC in (continued)

PALO VERDE UNITS 1.2.3 B 2.1.1-3 REVISION 21

STE-MODES 1 and 2 B 3.1.10 BASES APPLICABLE SAFETY ANALYSES (continued)

PHYSICS TESTS meet the criteria for inclusion in the Technical Specifications. since the component and process variable LCOs suspended during PHYSICS TESTS meet Criteria 1, 2. and 3 of 10 CFR 50.36 (c)(2)(ii).

LCO This LCO permits individual CEAs to be positioned outside of their normal group heights and insertion limits during the performance of PHYSICS TESTS. such as those required to:

a. Measure CEA worth:
b.

Determine the reactor stability index and damping factor under xenon oscillation conditions:

c.

Determine power distributions for nonnormal CEA configurations:

d. Measure rod shadowing factors: and
e.

Measure temperature and power coefficients.

Additionally, it permits the center CEA to be misaligned during PHYSICS TESTS required to determine the isothermal temperature coefficient (ITC). MTC. and power coefficient.

The requirements of LCO 3.1.4, LCO 3.1.5. LCO 3.1.6.

LCO 3.1.7. LCO 3.1.8. LCO 3.2.2, LCO 3.2.3. LCO 3.2.5 and LCO 3.3.3. may be suspended during the performance of PHYSICS TESTS provided THERMAL POWER is restricted to test power plateau, which shall not exceed 85% RTP.

APPLICABILITY This LCO is applicable in MODES 1 and 2 because the reactor must be critical at various THERMAL POWER levels to perform the PHYSICS TESTS described in the LCO section.

Limiting the test power plateau to < 85% RTP ensures that LHRs are maintained within acceptable limits.

I~b 6 tp 1

(continued)

PALO VERDE UNITS 1.2,3 B 3.1.10-4 REVISION 0

STE-MODES 1 and 2 B 3.1.10 BASES (continued)

ACTIONS A.1 If THERMAL POWER exceeds the test power plateau in MODE 1.

THERMAL POWER must be reduced to restore the additional thermal margin provided by the reduction. The 15 minute Completion Time ensures that prompt action shall be taken to reduce THERMAL POWER to within acceptable limits.

B.1 and B.2 If Required Action A.1 cannot be completed within the required Completion Time. PHYSICS TESTS must be suspended within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Allowing 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for suspending PHYSICS TESTS allows the operator sufficient time to change any abnormal CEA configuration back to within the limits of LCO 3.1.5.

LCO 3.1.6, and LCO 3.1.7. Suspension of PHYSICS TESTS exceptions requires restoration of each of the applicable LCOs to within specification.

SURVEILLANCE SR 3.1.10.1 REQUIREMENTS Verifying that THERMAL POWER is equal to or less than that allowed by the test power plateau, as specified in the PHYSICS TEST procedure and required by the safety analysis.

ensures that adequate LHR and departure from nucleate boiling ratio margins are maintained while LCOs are suspended. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Frequency is sufficient. based upon the slow rate of power change and increased operational controls in place during PHYSICS TESTS. Monitoring LHR ensures that the limits are not exceeded.

(continued)

PALO VERDE UNITS 1.2.3 B 3.1.10-5 REVISION 0

Technical Specification Bases 3.1.10 Surveillance Requirements Insert SR 3.1.10.2 Verification of the position of each partially or fully withdrawn full strength, part length, or part strength CEA is necessary to ensure that the minimum negative reactivity requirements for insertion on a trip are preserved. A 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Frequency is sufficient for the operator to verify that each CEA position is within the acceptance criteria.

INSERT PAGE B3.1.10-5

MSIVs B 3.7.2 BASES (continuu e

d

)

a APPLICABILITY The MSIVs must be OPERABLE in M}E 1 and in MODES 2, 3 and 4 except when all MSIVs are close when there is significant mass and energy in the RCS and steam generators. When the MSIVs are closed, they are already performing their safety function.

In MODES 5 and 6, the steam generators do not contain much energy because their temperature is below the boiling point of water: therefore, the MSIVs are not required for isolation of potential high energy secondary system pipe breaks in these MODES.

ACTIONS A.1 and A.2 With one MSIV inoperable in MODE 1. time is allowed to restore the component to OPERABLE status. Some repairs can be made to the MSIV with the unit hot. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is reasonable, considering the probability of an accident occurring during the time period that would require closure of the MSIVs.

The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time is consistent with that normally allowed for containment isolation valves that isolate a closed system penetrating containment. These valves differ from other containment isolation valves in that the closed system provides an additional means for containment isolation.

(continued)

PALO VERDE UNITS 1.2.3 B 3.7.2-4 REVISION 0

MFIVs B 3.7.3 BASES APPLICABILITY The MFIVs must be OPERABLE whenever there is significant mass and energy in the Reactor Coolant System and steam generators. This ensures that, in the event of an HELB, a single failure cannot result in the blowdown of more thaW one steam generator.

n IVA In MODES 1. 2. 3, and 4, the MFIVs are required to be OPERABLE, except when they are closed or isolated by a deactivated and closed power operated valve, in order to limit the amount of available fluid that could be added to containment in the case of a secondary system pipe break inside containment. When the valves are closed or isolated by a closed power operated valve, they are already performing their safety function.

I In MODES 5 and 6. steam generator energy is low.

the MFIVs are not required.

Therefore.

ACTIONS The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each penetration flow path.

A.1 and A.2 With one MFIV inoperable, action must be taken to close or isolate, QZ e it the inoperable valves within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

When tnese valves are closed or isolated. Co C5 3 ii they are performing their required safety futnction (e.g., to isolate the line).

The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time takes into account the redundancy afforded by-the remaining OPERABLE valves, and the low probability of an event occurring during this time period that would require isolation of the MFW flow paths.

Inoperable MFIVs that are closed to comply with Required Action A.1 must be verified on a periodic basis to be closed. This is necessary to ensure that the assumptions in the safety analysis remain valid. The seven day completion time is responsible, based on engineering judgement, MFIV status indications available in the control room. and other administrative controls, to ensure these valves are Qe'arXvat~r`F~in the closed position.

(continued)

I PALO VERDE UNITS 1.2.3 B 3.7.3-3 REVISION 1 PALO VERDE UNITS 1,2,3 B 3.7.3-3 REVISION 1

AC Sources - Operating B 3.8.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.8.1.2 and SR 3.8.1.7 These SRs help to ensure the availability of the standby electrical power supply to mitigate DBAs and transients and to maintain the unit in a safe shutdown condition.

To minimize the wear on moving parts that do not get lubricated when the engine is not running, these SRs are modified by a Note to indicate that all DG starts for these Surveillances may be preceded by an engine prelube period and followed by a warmup period prior to loading.

For the purposes of SR 3.8.1.2 and SR 3.8.1.7 testing. the DGs are started from standby condition. Standby conditions for a DG mean that the engine lube oil and coolant temperatures are maintained consistent with manufacturer recommendations.

Additionally, during standby conditions the diesel engine lube oil is circulated continuously and the engine coolant is circulated on and off via thermostatic control.

In order to reduce stress and wear on diesel engines, the DG manufacturer recommends a modified start in which the starting speed of DGs is limited, warmup is limited to this lower speed. and the DGs are gradually accelerated to synchronous speed prior to loading. This is the intent of Note 3. which is only applicable when such modified start procedures are recommended by the manufacturer.

rhe steady stat voltage and fyequency limit in SR 3.8.1.2 have not been justed for itrument accur cy. The analyzed valu s for the ste dy-state diesey generator voltage limi s are 2 4000

<d 4377.2 vo ts and the analyzed v ues for the s eady-state die el generator frequency imits are 2 5.7 and < 60.7 ertz.

The indi ated steady s te diesel ge rator voltage nd frequency lPits, using tie panel mount diesel gener or instrumenta on and adjust d for instrumet error, are 4080 and < 430 volts (Ref. 2), and 2 59 and < 60.5 h tz (Ref. 13),

resp ctively. If gital Mainten ce and Testing quipment (M E) is used ins ead of the par1 mounted dies generator i trumentation. he instrument rror may be reduced.

creasing the nge for the i icated steady ate voltage nd frequency mits.

(continued)

PALO VERDE UNITS 1.2.3 B 3.8.1-23 REVISION 20

AC Sources -

Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.2 and SR 3.8.1.7 (continued)

REQUIREMENTS SR 3.8.1.7 Note 2 stated~that the steady state voltage and frequency limits are analyzed values and have not been adjusted for instrument accuracy. The analyzed values for the steady-state diesel generator voltage limits are 2 4000 and < 4377.2 volts and the analyzed values for the steady-state diesel generator frequency limits are 2 59.7 and s 60.7 hertz.

The indicated steady state diesel generator voltage and frequency limits, using the panel mounted diesel generator instrumentation and adjusted for instrument error.

are 2 4080 and s 4300 volts (Ref. 12). and 2 59.9 and 5 60.5 hertz (Ref. 13). respectively. If digital Maintenance and Testing Equipment (M&TE) is used instead of the panel mounted diesel generator instrumentation, the instrument error may be reduced, increasing the range for the indicated steady state voltage and frequency limits.

SR 3.8.1.7 requires that. at a 184 day Frequency, the DG starts from standby conditions with the engine at normal keep-warm conditions and achieves required voltage and frequency within 10 seconds, and subsequently achieves steady state required voltage and frequency ranges. The 10 second start requirement supports the assumptions of the design basis LOCA analysis in the FSAR. Chapter 15 (Ref. 5).

A minimum voltage and frequency is specified rather than an upper and a lower limit because a diesel engine acceleration at full fuel (such as during a fast start) is likely to "overshoot" the upper limit initially and then go through several oscillations prior to a voltage and frequency within the stated upper and lower bounds. The time to reach "steady state" could exceed 10 seconds, and be cause to fail the SR.

However, on an actual emergency start, the EDG would reach minimum voltage and frequency in < 10 seconds at which time it would be loaded. Application of the load will dampen the oscillations. Therefore, only specifying the minimum voltage and frequency (at which the EDG can accept load) demonstrates the necessary capability of the EDG to satisfy safety requirements without including a potential for failing the Surveillance.

While reaching minimum voltage and frequency (at which the DG can accept load) in < 10 seconds is an immediate test of OPERABILITY, the ability of the governor and voltage regulator to achieve steady state operation, and the time to do so are important indicators of continued OPERABILITY.

Therefore, the time to achieve steady state voltage and (continued)

PALO VERDE UNITS 1,2.3 B 3.8.1-24 REVISION 20

DC Sources - Operating B 3.8.4 BASES BACKGROUND The DC power distribution system is described in more detail (continued) in the Bases for LCO 3.8.9, "Distribution Systems-Operating." and for LCO 3.8.10. "Distribution Systems -

Shutdown."

Each battery has adequate storage capacity to carry the required load continuously for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as discussed in the UFSAR. Chapter 8 (Ref. 4).

Each 125 VDC battery is separately housed in a ventilated room apart from its charger and distribution centers.

Each subsystem is located in an area separated physically and electrically from the other subsystem to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. There is no sharing between redundant Class lE subsystems, such as batteries, battery chargers, or distribution panels.

In addition, each DC electrical power subsystem contains a backup battery charger which is manually transferable to either channel of a subsystem. The transfer mechanism is mechanically interlocked to prevent both DC channels of a subsystem from being simultaneously connected to the backup battery charger.

The batteries for Train A and Train B DC electrical power subsystems are sized to produce required capacity at 80%

( Iov specv ic grVi ty cels) orQ0% (AA& I of nameol ate ating. Ie volage limit is 2.

cell 3j)1 f !ci

)

ray1

, which corresponds to a totl minimum voltage output of 128 V per battery peci~j cravit cel -

or 01V p at~

discussed in the Design Basis Manual (Ref. 12).

Each Train A and Train B DC electrical power subsystem has ample power output capacity for the steady state operation of connected loads required during normal operation, while at the same time maintaining its battery bank fully charged.

Each battery charger also has sufficient capacity to restore the battery from the design minimum charge to its fully charged state within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while supplying normal steady state loads discussed in the UFSAR, Chapter 8 (Ref. 4).

(continued)

PALO VERDE UNITS 1.2.3 B 3.8.4-2 REVISION 0

DC Sources -

Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.8 (continued)

REQUIREMENTS The modified performance discharge test is a simulated duty cycle consisting of just two rates: the one minute rate published for the battery or the largest current load of the duty cycle (but in no case lower than the performance test rate), followed by the test rate employed for the performance test, both of which envelope the duty cycle of the service test. Since the ampere-hours removed by a rated one minute discharge represents a very small portion of the battery capacity. the test rate can be changed to that for the performance test without compromising the results of the performance discharge test.

A modified discharge test is a test of the battery capacity and its ability to provide a high rate, short duration load (usually the highest rate of the duty cycle). This will often confirm the battery's ability to meet the critical period of the load duty cycle, in addition to determining its percentage of rated capacity.

Initial conditions for the modified performance discharge test should be identical to those specified for a service test.

Either the battery performance discharge test or the modified performance discharge test is acceptable for satisfying SR 3.8.4.8. In addition, either of the performance discharge tests may be used to satisfy SR 3.8.4.8 while satisfying the requirements of SR 3.8.4.7 at the same time, because the test parameters envelope the service test described in SR 3.8.4.7.

The acceptance criteria for this Surveillance are consistent with IEEE-450 (Ref. 9) and IEEE-485 (Ref. 5).

These references recommend that the battery be replaced if its capacity is below 80% of the manufacturer ratinq. A capacity of 80%

w speciic qr it 7lls) o 90% (A=&T))

shows that the battery rate of deterioration is increasing, even if there is ample capacity to meet the load requirements.

The Surveillance Frequency for this test is normally 60 months. If the battery shows degradation, or if the battery has reached 85% of its expected life and capacity is

< 100% of the manufacturer's rating, the Surveillance Frequency is reduced to 12 months. However, if the battery shows no degradation but has reached 85% of its expected (continued)

PALO VERDE UNITS 1,2.3 B 3.8.4-10 REVISION 2

DC Sources - Operating B 3.8.4 BASES SURVEILLANCE SR 3.8.4.8 (continued)

REQUIREMENTS life, the Surveillance Frequency is only reduced to 24 months for batteries that retain capacity 2 100% of the manufacturer's rating. Degradation is indicated when the battery capacity drops by more than 10% A1Vs Spocit]Q lgravyTt ce s) or/!%

relative to its capacity on the previous erformance test, or when it is 2 10% Cldw spegfic

~i thy cells) or k 5% W&U below the manufacturer's

'rating.

This SR is modified by a Note. The reason for the Note is that performing the Surveillance would Perturb the electrical distribution system and challenge safety systems.

REFERENCES

1.

10 CFR.50. Appendix A. GDC 17.

2. Regulatory Guide 1.6. March 10. 1971.
3.

IEEE-308-1974.

4.

UFSAR, Chapter 8.3.2.

5.

IEEE-485-1983, June 1983.

6.

UFSAR. Chapter 6.

7.

UFSAR. Chapter 15.

8.

Regulatory Guide 1.93, December 1974.

9.

IEEE-450-1980.

10.

Regulatory Guide 1.32, Revision 0. August 11, 1972.

11.

Regulatory Guide 1.129. Revision 1. February 1978.

12.

Design Basis Manual "Class lE 125 VDC Power System".

13.

Calculation 1.2.3ECPK207 PALO VERDE UNITS 1.2,3 B 3.8.4-11 REVISION 2

Battery Cell Parameters B 3.8.6 BASES SURVEILLANCE Table 3.8.6-1 (continued)

REQUIREMENTS effects. In addition to this allowance, footnote (a) to Table 3.8.6-1 permits the electrolyte level to be above the specified maximum level during equalizing charge, provided it is not overflowing.

These limits ensure that the plates suffer no physical damage, and that adequate electron transfer capability is maintained in the event of transient conditions.

IEEE-450 (Ref. 3) recommends that electrolyte level readings should be made only after the battery has been at float charge for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The Category A limit specified for float voLtage is Ž 2.13 V peL cell oF spe ic qraY tv ceils os >..

y Xer 9aI I z

This value is based on the battery vendor recommendation which states that prolonged operation of cells < 2.13 V6(N s~e Xfic gra tv ce ls) oY < 2.ZD can reduce the life expectancy of cells.

The Category A limit specified for sDecific gravity for each pilot cell is 2 1.200( lo speoific qr jitv cells) c/ > 1/29

(

(0.015 o s ecific gr vity callsl oP1O.Ol YATA below the vendbr fully charged nominal specific gravity or a battery charging current that had stabilized at a low value).

This value is characteristic of a charged cell with adequate capacity. According to IEEE-450 (Ref. 3). the specific gravity readings are based on a temperature of 770F (250C).

The specific'gravity readings are corrected for actual electrolyte temperature and level.

For each 30F (1.670C) above 770F (250C), 1 point (0.001) is added to the reading:

1 point is subtracted for each 3YF below 770F. The specific gravity of the electrolyte in a cell increases with a loss of water due to electrolysis or evaporation.

Category B defines the normal parameter limits for each connected cell. The term "connected cell" excludes any battery cell that may be jumpered out.

The Category B limits specified for electrolyte level and float voltage are the same as those specified for Category A and have been discussed above.

Footnote (d) to Table 3.8.6-1 is applicable to Category B float voltage.

Footnote (d) requires correction for average electrolyte temperature. The Category B limit specified for specific gravity for each connected cell is 2 1.195 1kl s p1 lTic qrvity ce ls) orl X1.2YU (Al" (0.020 below the vendor fully charged, nominal (continued)

PALO VERDE UNITS 1.2.3 B 3.8.6-5 REVISION 6

Battery Cell Parameters B 3.8.6 BASES SURVEILLANCE Table 3.8.6-1 (continued)

REQUIREMENTS specific gravity) with the average of all connected cells lŽ2 1.2051(lon specTfic gratity rells) nf > 1-290 (Aim (0.010 below thTe vendor fully charged, nominal specific gravity).

These values are based on vendor's recommendations.

The minimum specific gravity value required for each cell ensures that the effects of a highly charged or newly installed cell will not mask overall degradation of the battery.

Category C defines the limit for each connected cell. These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function and maintain a margin of safety. When any battery parameter is outside the Category C limit, the assurance of sufficient capacity described above no longer exists and the battery must be declared inoperable.

The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value

-for float voltage is based on vendor recommendations which state that a cell voltage of 2.07 V or belowwrm SpE Ficl (ralitv ce--es) or 2.A4 V or b (A}ST, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement.

The Category C limit of average specific gravity 2 1.195 KIeci c r1t cells) er > 1 80 (M&T) is based on vendor recommendations (0.020 below the vendor recommended fully charged, nominal specific gravity).

In addition to that limit, it is required that the specific gravity for each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery.

Footnotes (b) and (c) to Table 3.8.6-1 are applicable to Category A. B. and C specific gravity.

Footnote (b) to Table 3.8.6-1 requires specific gravity correction for electrolyte level and temperature, with the exception that level correction is not required when battery charging current is < 2 amps on float charge. This current provides, in general, an indication of overall battery condition.

(continued)

PALO VERDE UNITS 1.2.3 B 3.8.6-6 REVISION 6

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