ML17173A877
| ML17173A877 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/22/2017 |
| From: | Lacal M Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-07513-MLL/TNW | |
| Download: ML17173A877 (49) | |
Text
10 CFR 50.90 Qaps 102-07513-MLI7TNW June 22, 2017 MARIA L. LACAL Senior Vice President, Nuclear Regulatory & Oversight Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel 623.393.6491 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removai & Ciarify SR Usage Ruie Appiication to Section 5.5 Testing Pursuant to 10 CFR 50.90, Arizona Public Service Company (APS) is submitting a request for an amendment to the Technical Specifications (TS) for Palo Verde Nuclear Generating Station (PVNGS), Units 1, 2, and 3.
The proposed change revises the TS to eliminate Section 5.5.8, Inservice Testing Program.
A new defined term, "Inservice Testing Program," is added to the TS Definitions section.
This request is consistent with TSTF-545, Revision 3, TS Inservice Testing Program Removai
& Clarify SR Usage Rule Application to Section 5.5 Testing.
The Enclosure provides a description and assessment of the proposed license amendment. of the Enclosure provides proposed TS changes (mark-up). Attachment 2 of the Enclosure provides revised TS (clean) pages. Attachment 3 of the Enclosure provides proposed TS Bases changes (mark-up) for information only.
Approval of the proposed amendment is requested within one year from date of submittal.
Once approved, the amendment shall be implemented within 120 days.
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).
No new commitments are being made in this submittal.
If there are any questions or if additional information is needed, please contact Michael D.
DiLorenzo, Licensing Section Leader, at (623) 393-3495.
A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
102-07513-ML17TNW ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Application to Revise Technical Specifications to Adopt TSTF-545 Page 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed on June 22. 2017 (Date)
Sincerely, Lacal, Maria UZ06149)
Digitally signed by Lacal, Maria L(Z06149)
DN: cn=Lacal, Maria MZ06149)
Date: 2017.06.22 09:49:17
-07'00' MLITTNW/sma
Enclosure:
Description and Assessment of Technical Specifications Changes cc:
K. M. Kennedy S. P. Lingam M. M. Watford C. A. Peabody T. Morales NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency (ARRA)
Enclosure Description and Assessment of Proposed License Amendment
Enclosure Description and Assessment of Proposed License Amendment
Subject:
Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing
- 1.
DESCRIPTION
- 2.
ASSESSMENT 2.1 Applicability of Published Safety Evaluation 2.2 Variations
- 3.
REGULATORY ANALYSIS 3.1 No Significant Hazards Consideration Determination
- 4.
ENVIRONMENTAL EVALUATION ATTACHMENTS:
- 1.
Proposed Technical Specification Changes (Mark-Up)
- 2.
Revised Technical Specification Pages (Clean)
- 3.
Proposed Technical Specification Bases Changes (Mark-Up) -
Information Only
Enclosure Description and Assessment of Proposed License Amendment
1.0 DESCRIPTION
The proposed change eliminates the Palo Verde Nuclear Generating Station (PVNGS)
Technical Specifications (TS), Section 5.5.8, Insen/ice Testing Program, to remove requirements duplicated in American Society of Mechanical Engineers (ASME) Code for Operations and Maintenance of Nuclear Power Plants (OM Code), Code Case OMN-20, Inservice Test Frequency. A new defined term. Inservice Testing Program, is added to TS Section 1.1, Definitions. The proposed change to the TS is consistent with TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
2.0 ASSESSMENT
2.1 Applicability of Published Safety Evaluation Arizona Public Service (APS) has reviewed the model safety evaluation provided to the Technical Specifications Task Force in a letter dated October 11,2015 (NRC ADAMS Accession No. ML15314A305). This review included a review of the NRC staffs evaluation, as well as the information provided in TSTF-545. APS concludes that the justifications presented in TSTF-545, and the model safety evaluation prepared by the NRC staff are applicable to PVNGS Units 1,2, and 3 and justify this amendment for the incorporation of the changes into the PVNGS TS.
APS was issued construction permits for PVNGS Units 1,2 and 3 on May 25, 1976 (No.
CPPR-141, 142, and 143, respectively) and the provisions of 10 CFR 50.55a(f)(3) are applicable.
2.2 Variations APS proposes the following variations from the TS changes described in TSTF-545.
These variations are administrative and do not affect the applicability of TSTF-545 to the proposed license amendment.
APS proposes that the Inservice Testing (1ST) program in TS 5.5.8 be deleted and subsequent sections not be renumbered. By maintaining the current program numbering and references the administrative burden to update station procedure references is avoided.
In addition, PVNGS specific TS LCO numbering is maintained since there are some TS components in TSTF-545 that are not in the PVNGS design.
Enclosure Description and Assessment of Proposed License Amendment
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination APS requests adoption of the Technical Specification (TS) changes described in TSTF-545, TS Insen/ice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, which is an approved change to the Improved Standard Technical Specifications (ISTS), into the PVNGS, Units 1,2, and 3 TS. The proposed change revises the TS Chapter 5, Administrative Controls, Section 5.5, Programs and Manuals, to delete Section 5.5.8, Inservice Testing Program specification.
Requirements in the 1ST Program are removed, as they are duplicative of requirements in the American Society of Mechanical Engineers (ASME) Operations and Maintenance (OM) Code, as clarified by Code Case OMN-20, Inservice Test Frequency. Other requirements in Section 5.5 are eliminated because the Nuclear Regulatory Commission (NRC) has determined their appearance in the TS is contrary to regulations. A new defined term. Inservice Testing Program, is added, which references the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, paragraph 50.55a(f).
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 amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change revises Chapter 5, Administrative Controls, Section 5.5, Programs and Manuals, by eliminating the Inservice Testing Program specification. Requirements in the 1ST Program are removed, as they are duplicative of requirements in the ASME OM Code, as clarified by Code Case OMN-20, Inservice Test Frequency. Other requirements in Section 5.5.8, Inservice Testing Program are eliminated because the NRC has determined their inclusion in the TS is contrary to regulations. A new defined term. Inservice Testing Program, is added which references the requirements of 10 CFR 50.55a(f).
Performance of inservice testing is not an initiator to any accident previously evaluated. As a result, the probability of occurrence of an accident is not significantly affected by the proposed change. Inservice test periods under Code Case OMN-20 are equivalent to the current testing period allowed by the TS with the exception that testing periods greater than two years may be extended by up to six months to facilitate test scheduling and consideration of plant operating conditions that may not be suitable for performance of the required testing. The
Enclosure Description and Assessment of Proposed License Amendment testing period extension will not affect the ability of the components to mitigate any accident previously evaluated as the components are required to be operable during the testing period extension. Performance of inservice tests utilizing the allowances in Code Case OMN-20 will not significantly affect the reliability of the tested components. As a result, the availability of the affected components, as well as their ability to mitigate the consequences of accidents previously evaluated, is not affected.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not alter the design or configuration of the plant. The proposed change does not involve a physical alteration of the plant; no new or different kind of equipment will be installed. The proposed change does not alter the types of inservice testing performed. In most cases, the frequency of inservice testing is unchanged. However, the frequency of testing would not result in a new or different kind of accident from any previously evaluated since the testing methods are not altered.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed change eliminates some requirements from the TS in lieu of requirements in the ASME Code, as modified by use of Code Case OMN-20.
Compliance with the ASME Code is required by 10 CFR 50.55a. The proposed change also allows inservice tests with periods greater than two years to be extended by six months to facilitate test scheduling and consideration of plant operating conditions that may not be suitable for performance of the required testing. The testing period extension will not affect the ability of the components to respond to an accident as the components are required to be operable during the testing period extension. The proposed change will eliminate the existing TS SR 3.0.3 allowance to defer performance of missed inservice tests up to the duration of the specified testing period, and instead will require an assessment of the missed test on equipment operability. This assessment will consider the effect on a margin of safety (equipment operability). Should the component be
Enclosure Description and Assessment of Proposed License Amendment inoperable, the Technical Specifications provide actions to ensure that the margin of safety is protected. The proposed change also eliminates a statement that nothing in the ASME Code should be construed to supersede the requirements of any TS. The NRC has determined that statement to be incorrect.
However, elimination of the statement will have no effect on plant operation or safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, APS concludes that the proposed amendment does not involve a 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.
4.0 ENVIRONMENTAL EVALUATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
Enclosure Description and Assessment of Proposed License Amendment ATTACHMENT 1 Proposed Technical Specification Changes (Mark-Up)
Pages:
1.1-4 3.4.10- 2 3.4.11-2 3.4.13-3 3.53-2 3.6.3-6 3.6.6-2 3.7.1-3 3.7.2-3 37.3-2 37.5-3 5.5-5
1.1 Definitions Definitions 1.1 DOSE EQUIVALENT XE-133 (continued) be performed using effective dose conversion factors for air submersion listed in Table B-1 of Regulatory Guide 1.109, Rev. 1, NRC, 1977.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e.. the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
NSERVICE TESTING The INSERVICE TESTING PROGRAM is the licensee PROGRAM orooram that fulfills the reouirements of 10 CFR 50.55am.
K., is the K effective calculated by considering the actual CEA configuration and assuming that the fully or partially inserted full strength CEA of highest worth is fully withdrawn.
LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;
- 2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or PALO VERDE UNITS 1,2,3 1.1-4 (continued)
AMENDMENT NO. 4<<2,
Pressurizer Safety Valves-MODES 1, 2, and 3 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in accordance with the tnservice Testing PfooramlNSERVICE In accordance with PfoofamlNSERVICE TESTING PROGRAM. Fol owina testina. lift TESTING PROGRAM settings sha 1 be within +/- 1%.
PALO VERDE UNITS 1,2,3 3.4.10-2 AMENDMENT NO. 44^
Pressurizer Safety Valves-MODE 4 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify the required pressurizer safety valve is OPERABLE in accordance RreQf^lhfsBRVICE^TESTI NG PROGRAM. Followina testing, lift settings shall be within +/- 1%.
In accordance with the ISr^lNSERVICE TESTING PROGRAM OD O
-M O Mr>>TP In accordance with the Surveillance Frequency Control Program Only required to be performed when a Shutdown Cooling System suction line relief valve is being used for overpressure protection.
Verify the required Shutdown Cooling System suction line relief valve is aligned to provide overpressure protection for the RCS.
SR 3.4.11.3 Verify the required Shutdown Cooling System suction line relief valve is OPERABLE with the required setpoint.
In accordance with the ISf^INSE^ICE TESTING PROGRAM PALO VERDE UNITS 1,2,3 3.4.11-2 AMENDMENT NO. 4#8,
LTOP System 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify RCS Vent >16 square inches is open.
In accordance with the Surveillance Frequency Control Program SR 3.4.13.2 Verify each Shutdown Cooling System suction line relief valve is aligned to provide overpressure protection for the RCS.
In accordance with the Surveillance Frequency Control Program SR 3.4.13.3 Verify each Shutdown Cooling System suction line relief valve is OPERABLE with the required setpoint.
In accordance with the TESTING PROGRAM.
PALO VERDE UNITS 1,2,3 3.4.13-3 AMENDMENT NO. 4<<8.
ECCS Operating 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify each ECCS manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program SR 3.5 3.2 Verify ECCS piping is full of water.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.3 Verify each ECCS pump develops the required differential pressure at the flow test point.
In accordance Toting PreeramlNSERVI CE TESTING PROGRAM SR 3.5.3.4 Verify each ECCS automatic valve that is not lock^, sealed, or othen/vise secured in position, in the flow path actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.5 Verify each ECCS pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.6 Verify each LPSI pump stops on an actual or simulated actuation signal.
1.1.1.1 In accordance with the Surveillance Frequency PALO VERDE UNITS 1,2,3 3.5.3-2 AMENDMENT NO. m,
Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.3.4
-NOTE-Valves and blind flanges in high radiation areas may be verified by use of administrative means.
Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed or othenwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days SR 3.6.3.S Verify the isolation time of each required automatic power operated containment isolation valve is within limits.
In accordance with the Inservise Testmg PfeofamlNSERVICE TESTING PROGRAM SR 3.6.3.6 Perform leakage rate testing for re<quired containment purge valves with resilient seals.
In accordance with the Surveillance Frequency Control Program AND Within 92 days after opening the valve SR 3.6.3.7 Verify each required automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program PALO VERDE UNITS 1,2,3 3.6.3-6 AMENDMENT NO. 468,
Containment Spray System 3.6.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.2 Verify the containment spray piping is full of water to the 113 ft level in the containment spray header.
In accordance with the Surveillance Frequency Control Program SR 3.6 6.3 Verify each containment spray pumps developed head at the flow test point is greater than or equal to the required developed head.
In accordance with the In service Testing PfGQfamlNSERVICE TESTING PROGRAM SR 3.6.6.4 Verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.5 Verify each containment spray pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.6 Verify each spray nozzle is unobstructed.
In accordance with the Surveillance Frequency Control Program PALO VERDE UNITS 1,2,3 3.6.6-2 AMENDMENT NO. 468,
MSSVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OD 0-744 Kiryrc Not required to be performed prior to entry into MODE 3.
Verify each required MSSV lift setpoint per Testing ProaramlNSERVICE TESTING In accordance with the PROGRAM. Following testing, lift settings shall be within +/- 1%.
r 1 CIM 1 INSERV CE TESTING PROGRAM PALOVERDE UNITS 1,2,3 3.7.1-3 AMENDMENT NO. 447. 455"
MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY op Q 7 *5 )
MOTC In accordance with the Inservice Not required to be performed prior to entry into MODE 3.
Verify closure time of each MSIV is within limits with each actuator train on an actual or simulated actuation signal.
INSERVICE TESTING PROGRAM PALO VERDE UNITS 1,2,3 3.7.2-3 AMENDMENT NO. Am
MFIVs 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.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 not met.
AND C.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 /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFIV is within limits on an actual or simulated actuation signal.
In accordance INSERVICE TESTING PROGRAM PALO VERDE UNITS 1,2.3 3.7.3-2 AMENDMENT NO. W
AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and automatic valve in each water flow path and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program qp o 7 c 9 Kinxc In accordance with the Inservioe Test Program INSERVICE Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reaching 532F in the RCS.
Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.
TESTING PROGRAM OD <1 7 C -a KiriTCC In accordance with the Surveillance Frequency Control Program
- 1.
Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reaching 532F in the RCS.
- 2.
Not applicable in MODE 4 when steam generator is relied upon for heat removal.
Verify each AFW automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
(continued)
PALO VERDE UNITS 1,2,3 3.7.S-3 AMENDMENT NO. 4§.
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of regulatory position c.4.b of Regulatory Guide 1.14, Revision 0, October 1971.
5.5.8 Inservice Testing ProqramDeleted
-T-his-program provides oontrels for-inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the followings
-a^----- Testing frequencies applicable to the ASME Code for Operation and ASME OM Code and terminology for-------------------------- Required Frequencies aetivities----------------------- ----------- testino activities------
Weekly------------------------ -----------At least once per7-days Af Ickoof
Quarterly or every
Semiannually-Of A*
r\\r\\r^A r\\t!ir d Q/i rloi/o
Bionnially or every
2 years---------------------- ---------At least once per 731 days Frequencies and to other normal and aseelerated Frequencies specified as 2 years or less in the Inservioe Testing Program for
-&----- The provisions of SR-3-.OT^^re-applioable to inservioe testing activities; arrd
-dt----- Nothing in the ASM&-OM Code shall be construed to supersede the requirements of any TS.
(continued)
PALO VERDE UNITS 1,2,3 5.5-5 AMENDMENT NO. 484
Enclosure Description and Assessment of Proposed License Amendment ATTACHMENT 2 Revised Technical Specification Pages (Clean)
Pages:
1.1-4 3.4.10- 2 3.4.11-2 3.4.13-3 3.53-2 3.63-6 3.66-2 3.7.1-3 3.7.2-3 3.7.3-2 3.7.S-3 5.5-5
Definitions 1.1 1.1 Definitions DOSE EQUIVALENT XE-133 be performed using effective dose conversion (continued) factors for air submersion listed in Table B-1 of Regulatory Guide 1.109, Rev. 1, NRC, 1977.
ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.
INSERVICE TESTING PROGRAM The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f),
is the K effective calculated by considering the actual CEA configuration and assuming that the fully or partially inserted full strength CEA of highest worth is fully withdrawn.
LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;
- 2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; or PALO VERDE UNITS 1,2,3 1.1-4 (continued)
AMENDMENT NO. 4<<2,
Pressurizer Safety Valves-MODES 1, 2, and 3 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance with OPERABLE in accordance vrith the the INSERVICE INSERVICE TESTING PROGRAM.
TESTING PROGRAM Following testing, lift settings shall be within +/- 1%.
PALO VERDE UNITS 1,2,3 3.4.10-2 AMENDMENT NO. 447
Pressurizer Safety Valves-MODE 4 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify the required pressurizer safety valve is OPERABLE in accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within +/- 1%.
In accordance with the INSERVICE TESTING PROGRAM CD 0 ^
o MOTF In accordance with the Surveillance Frequency Control Program Only required to be performed when a Shutdown Cooling System suction line relief valve is being used for overpressure protection.
Verify the required Shutdown Cooling System suction line relief valve is aligned to provide overpressure protection for the RCS.
SR 3.4.11.3 Verify the required Shutdown Cooling System suction line relief valve is OPERABLE with the required setpoint.
In accordance with the INSERVICE TESTING PROGRAM PALO VERDE UNITS 1,2,3 3.4.11-2 AMENDMENT NO. 488,
LTOP System 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify RCS Vent ^ 16 square inches is open.
In accordance with the Surveillance Frequency Control Program SR 3.4.13.2 Verify each Shutdown Cooling System suction line relief valve is aligned to provide overpressure protection for the RCS.
In accordance with the Surveillance Frequency Control Program SR 3.4.13.3 Verify each Shutdown Cooling System suction line relief valve is OPERABLE with the required setpoint.
In accordance with the INSERVICE TESTING PROGRAM.
PALO VERDE UNITS 1,2,3 3.4.13-3 AMENDMENT NO. 4<<8,
ECCS Operating 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 Verify each ECCS manual, power operated, and automatic valve in the f ow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.2 Verify ECCS piping is full of water.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.3 Verify each ECCS pump develops the required differential pressure at the flow test point.
In accordance with the INSERVICE TESTING PROGRAM SR 3.5.3.4 Verify each ECCS automatic valve that is not locked, sealed, or otherwise secured in position. In the flow path actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.5 Verify each ECCS pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.5.3.6 Verify each LPSI pump stops on an actual or simulated actuation signal.
1.1.1.1 In accordance with the Surveillance Frequency Control Program (continued)
PALO VERDE UNITS 1,2,3 3.53-2 AMENDMENT NO. 4<<8,
Containment Isolation Valves 3.6.3 SURVEILLANCE FREQUENCY OD 'i a o A moTF Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days Valves and blind flanges in high radiation areas may be verified by use of administrative means.
Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
SR 3.6.3.5 Verify the isolation time of each required automatic power operated containment isolation valve is within limits.
In accordance with the INSERVICE TESTING PROGRAM SR 3.6.3.6 Perform leakage rate testing for required containment purge valves with resilient seals.
In accordance with the Surveillance Frequency Control Program AND Within 92 days after opening the valve SR 3.6.3.7 Verify each required automatic containment isolation valve that is not locked, sealed, or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program PALOVERDE UNITS 1,2,3 3.6.3-6 AMENDMENT NO. W
Containment Spray System 3.6.6 SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify each containment spray manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.2 Verify the containment spray piping is full of water to the 113 ft level in the containment spray header.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.3 Verify each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head.
In accordance with the INSERVICE TESTING PROGRAM SR 3.6.6.4 Verify each automatic containment spray valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.5 Verify each containment spray pump starts automatically on an actual or simulated actuation signal.
In accordance with the Surveillance Frequency Control Program SR 3.6.6.6 Verify each spray nozzle is unobstructed.
In accordance with the Surveillance Frequency Control Program PALO VERDE UNITS 1,2,3 3.66-2 AMENDMENT NO. 4<<8,
MSSVs 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1
-.............................. NOTE..................
Not required to be performed prior to entry into MODE 3.
In accordance with the INSERVICE TESTING PROGRAM Verify each required MSSV lift setpoint per Table 3.7.1-2 in accordance with the INSERVICE TESTING PROGRAM. Following testing, lift settings shall be within +/- 1%.
PALO VERDE UNITS 1.2,3 3.7.1-3 AMENDMENT NO. 4^.
MSIVs 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OD 0 *7 O -1 MOTF In accordance with the INSERVICE TESTING PROGRAM Not required to be performed prior to entry into MODE 3.
Verify closure time of each MSIV is within limits with each actuator train on an actual or simulated actuation signal.
PALOVERDE UNITS 1,2,3 3.7.2-3 AMENDMENT NO. 4^
MFIVs 3.7.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.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 not met.
AND C.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 /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each MFIV is within limits on an actual or simulated actuation signal.
In accordance with the INSERVICE TESTING PROGRAM PALOVERDE UNITS 1,2,3 3.73-2 AMENDMENT NO. 4S4-
AFW System 3.7.5 SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and automatic valve in each water flow path and in both steam supply flow paths to the steam turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program OD Q T K O Kir>TF In accordance with the INSERVICE TESTING PROGRAM OK 0.1.""
...................1 Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reaching 532F in the RCS.
Verify the developed head of each AFW pump at the flow test point is greater than or equal to the required developed head.
on o -7 c -a KirsTcq In accordance with the Surveillance Frequency Control Program OK O./.O.O
- ------------ l>HJ 1 CO
- 1.
Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after reaching 532F in the RCS.
- 2.
Not applicable in MODE 4 when steam generator is relied upon for heat removal.
Verify each AFW automatic valve that is not locked, sealed, or othen/vise secured in position, actuates to the correct position on an actual or simulated actuation signal.
(continued)
PALO VERDE UNITS 1,2,3 S.7.5-3 AMENDMENT NO. 48,
Programs and Manuals, 5.5 5.5 Programs and Manuals (continued) 5.5.7 Reactor Coolant Pumo Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of regulatory position c.4.b of Regulatory Guide 1.14, Revision 0, October 1971.
5.5.8 Deleted (continued)
PALO VERDE UNITS 1,2,3 5.5-5 AMENDMENT NO. 484,
Enclosure Description and Assessment of Proposed License Amendment ATTACHMENT 3 Proposed Technical Specification Bases Changes (Mark-Up) - Information Only Pages:
B 3.0-16 B 3.0-18 B 3.0-19 B 3.4.10-4 B 3.4.11-5 B 3.4.13-10 B 3 5.3-9 B 3.6.3-18 B 3.6.6-7 B3.7.1-3 B3.7.1-5 B 3.7.2-8 B 3 7.3-5 B 3.7.5-9
SR Applic^Nity BASES B3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SRs SR 3.0.1 through SR 3.0.4 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated. SR 3.0.2 and SR 3.0.3 apply in Chapter 5 only when invoked bv a Chapter 5 Specification.
SR 3.0.1 SR 3.0.1 establishes the requirement that SRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO. Surveillances may be performed by means of any series of s^uential, overlapping, or total steps provided the entire Surveillance is performed within the specified Frequency. Additionally, the definitions related to instrument testing (e.g., CHANNEL CALIBRATION) specify that these tests are preformed by means of any series of sequential, overlapping, or total steps.
Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when:
- a.
The systems or components are known to be inoperable, although still meeting the SRs; or
- b.
The requirements of the Surveillance(s) are known to be not met between required Surveillance performances.
Surveillances do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. The SRs associated with a Special Test Exception (STE) are only applicable when the STE is used as an allowable exception to the requirements of a Specification.
(continued)
PALO VERDE UNITS 1,2,3 B 3.0-16 REVISION §0
BASES SR Applic^iHtg SR 3.0.2 SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..." interval.
SR 3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the Surveillance (e.g., transient conditions or other ongoing Surveillance or maintenance activities).
When a Section 5.5. Programs and Manuals. specification states that the provisions of SR 3.0.2 are applicable, a 25% extension of the testing interval, whether stated in the specification or incorporated by reference, is permitted.
The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency.
This is based on the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the SRs.
The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in the individual Specifications.
The requirements of regulations take precedence over the TS. An eExamples of where SR 3.0.2 does not apoIvTs-the-are the Containment Leakage Rate Testing Program required bv 10 CFR
- 50. Appendix J. and the inservice testing of pumps and valves in accordance with applicable American Society of Mechanical Engineers Operation and Maintenance Code, as required bv 10 CFR 50.55a. These programs establish testing requirements and Frequencies in accordance with the requirements of regulations.
Yhe TS cannot, in and of themselves, extend a test interval specified n the regulations directly or bv reference.
As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action, whether it is a particular Surveillance or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an alternative manner.
(continued)
PALO VERDE UNITS 1,2,3 B 3.0-18 REVISION 4©
BASES SR Applicability B 3.0 SR 3.0.2 The provisions of SR 3.0.2 are not intended to be used (continued) repeatedly merely as an operational convenience to extend Surveillance inten/als (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified.
SR 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met. Reference Bases Section 3.0.2 for discussion and applicability of Frequency and 25% extension.
When a Section 5.5. "Programs and Manuals." specification states that the provisions of SR 3.0.3 are applicable, it permits the flexibility to defer declaring the testing requirement not met in accordance with SR 3.0.3 when testing has not been completed within the testing interval (including the allowance of SR 3.0.2 if invoked bv the Section 5.5 specification^
This delay period provides an adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.
The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.
When a Surveillance with a Frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to entering MODE 1 after each fuel loading, or in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 3.0.3 allows for the full delay period of up to the specified Frequency to perform the Surveillance. However, since there is not a time interval (continued)
PALO VERDE UNITS 1,2,3 B 3.0-19 REVISION 49
Pressurizer Safety Valves-MODES 1, 2, and 3 B 3.4.10 BASES ACTIONS B.1 and B.2 (continued)
The change from MODE 1, 2, or 3 to MODE 4 reduces the RCS energy (core power and pressure), lowers the potential for large pressurizer insurges, and thereby removes the need for overpressure protection by four pressurizer safety valves.
SURVEILLANCE REQUIREMENTS SR 3.4.10.1 SRs are specified in the Inservice Testino-Pfoar-am INSERVICE TESTING PROGFtAM. Pressurizer safety valves are to be tested in accordance with the requirements of the ASME OM Code (Ref. 3),
which provides the activities and the Frequency necessary to satisfy the SRs. No additional requirements are specified.
The pressurizer safety valve setpoint is +3%, -1% for OPERABILITY; however, the valves are reset to +/- 1% during the Surveillance to allow for drift (Ref. 2). The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
REFERENCES
- 1.
ASME, Boiler and Pressure Vessel Code,Section III.
- 2.
PVNGS Operating License Amendment Nos. 75, 61, and 47 for Units 1,2, and 3, respectively, and associated NRG Safety Evaluation dated May 16, 1994.
- 3.
ASME Code for Operation and Maintenance of Nuclear Power Plants.
PALO VERDE UNITS 1,2,3 B 3.4.10-4 REVISION §4
Pressurizer Safety Valves-MODE 4 B 3.4.11 BASES (continued)
SURVEILLANCE SR 3.4.11.1 REQUIREMENTS TESTING PROGRAM. Pressurizer safety valves are to be tested in accordance with the requirements of the ASME OM Code (Ref. 2),
which provides the activities and the Frequency necessary to satisfy the SRs. No additional requirements are specified.
The pressurizer safety valve setpoint is +3%, -1% for OPERABILITY; however, the valves are reset to +/- 1% during the Surveillance to allow for drift (Ref. 3). The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
SR 3.4.11.2 SR 3.4.11.2 requires that the required Shutdown Cooling System suction line relief valve is OPERABLE by verifying its open pathway condition.
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
The SR has been modified by a Note that requires performance only if a Shutdown Cooling System suction line relief valve is being used for overpressure protection. The Frequencies consider operating experience with mispositioning of unlocked and locked pathway vent valves.
SR 3.4.11.3 SRs are specified in the INSERVICE TESTING PROGRAMInservice Testing Program. Shutdown Cooling System suction line relief valves are to be tested in accordance with the requirements of the ASME OM Code (Ref. 2), which provides the activities and the Frequency necessaiy to satisfy the SRs. The Shutdown Cooling System suction line relief valve setpoint is 467 psig.
PALO VERDE UNITS 1,2,3 B 3,4.11-5 (continued)
REVISION §§
LTOP System B 3.4.13 BASES SURVEILLANCE REQUIREMENTS SR 3.4.13-1 and 3.4.13.2 (continued)
For an RCS vent to meet the specified flow capacity, it requires removing all pressurizer safety valves, or similarly establishing a vent by opening the pressurizer manway (Ref. 10). The vent path(s must be above the level of reactor coolant, so as not to drain the RCS when open. The passive vent arrangement must only be open (vent pathway exists) to be OPERABLE. These Surveillances need only be performed if the vent or the Shutdown Cooling System suction line relief valves are being used to satisfy the requirements of this LCO. The Frequencies consider operating experience with mispositioning of unlocked and locked pathway vent valves, and passive pathway obstructions.
SR 3.4.13.3 TESTINg'?ROGRAM.^
Tccting Program Shutdown Cooling System suction line relief valves are to be tested in accordance with the requirements of the ASME OM Code (Ref. 9), which provides the activities and the Frequency necessary to satisfy the SRs. The Shutdown Cooling System suction line relief valve set point is 467 psig.
REFERENCES
- 1.
- 2.
- 3.
UFSAR, Section 15.
- 4.
- 5.
- 6.
- 7.
UFSAR, Section 5.2.
(continued)
PALO VERDE UNITS 1,2,3 B 3.4.13-10 REVISION §6
BASES ECCS - Operating B 3.5.3 SURVEILLANCE REQUIREMENTS (continued)
SR 3.S.3.3 Periodic surveillance testing of ECCS pumps to detect gross degradation caused by impeller structural damage or other hydraulic component problems is required by the ASME OM Code.
This type of testing may be accomplished by measuring the pump developed head at only one point of the pump characteristic curve.
This verifies both that the measured performance is within an acceptable tolerance of the original pump baseline performance and that the performance at the test flow is greater than or equal to the performance assumed in the unit safety analysis. SRs are specified in the Inservice Testing Program INSERVICE TESTING PROGRAM, which encompasses the ASME OM Code (Ref. 7).
SR 3.5.3.4. SR 3.5.3 5. and SR 3.5.3.6 These SRs demonstrate that each automatic ECCS valve actuates to the required position on an actual or simulated SIAS and on an RAS, that each ECCS pump starts on receipt of an actual or simulated SIAS, and that the LPSI pumps stop on receipt of an actual or simulated RAS. This Surveillance is not required for valves that are locked, sealed, or otherwise secured in the required position under administrative controls. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
The following valve actuations must be verified:
on an actual or simulated recirculation actuation signal, the containment sump isolation valves open, and the HPSI, LPSI and CS minimum bypass recirculation flow line isolation valves and combined SI mini flow valve close.
(continued)
PALO VERDE UNITS 1,2,3 B 3.5.3-9 REVISION S§
BASES Containment Isolation Valves B 3.6.3 SURVEILLANCE REQUIREMENTS SR 3.S.3.4 (continued) administrative controls and the probability of their misalignment is low. Containment isolation valves that are open under administrative controls are not required to meet the SR during the time that they are open. This SR does not apply to valves that are locked, sealed, or otherwise secured in the closed position, since these were verified to be in the correct position upon locking, sealing or securing.
The Note allows valves and blind flanges located in high radiation areas to be verified closed by use of administrative means. Allowing verification by administrative means is considered acceptable, since access to these areas is typically restricted during MODES 1, 2, 3 and 4 for ALARA reasons.
Therefore, the probability of misalignment of these containment isolation valves, once they have been verified to be in their proper position, is small.
SR 3.6.3.S Verifying that the isolation time of each required automatic power operated containment isolation valve is within limits is required to demonstrate OPERABILITY. The isolation time test ensures the valve will isolate in a time period less than or equal to that assumed in the safety analysis. The isolation time and Frequency INSERVICE TESTING PROGRAM.
SR 3.6.3 6 For required containment purge valves with resilient seals, additional leakage rate testing beyond the test requirements of 10 CFR 50, Appendix J, Option B (Ref. 5), is required to ensure OPERABILITY. Industry operating experience has demonstrated that this type of seal has the potential to degrade in a shorter time period than do other seal types. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
(continued)
PALO VERDE UNITS 1,2,3 B 3.6.3-18 REVISION m
BASES Containment Spray System B 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
SR 3.6.6.2 Verifying that the containment spray header piping is full of water to the 113 ft level minimizes the time required to nil the header.
This ensures that spray flow will be admitted to the containment atmosphere within the time frame assumed in the containment analysis. The analyses shows that the header may be filled with unborated water which helps to reduce boron plate out due to evaporation. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. The value of 113 ft is an indicated value which accounts for instrument uncertainty.
SR 3.6.6.3 Verifying that each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head ensures that spray pump performance has not degraded during the cycle. Flow and differential pressure are norma tests of centrifugal pump performance required by the ASME OM Code (Ref. 6). Since the containment spray pumps cannot be tested with flow through the spray headers, they are tested on recirculation flow (either full flow or miniflow as conditions permit). This test is indicative of overall performance.
Such inservice inspections confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. The Frequency of this SR is in accordance with the Inservice Testing-Preqram INSERVJCE TESTING PROGRAM.
(continued)
PALO VERDE UNITS 1,2,3 B 3.6.6-7 REVISION m
MSSVs B 3.7.1 BASES LCD (continued) overpressure, and reseat when pressure has been reduced.
The OPERABILITY of the MSSVs is determined by periodic SUrV6lilanC6 L6Sliny in aUv/UrUailoc WllH UIU mticfiviuo Proaram INSERVICE TESTING PROGRAM The lift settings, according to Table 3.7.1-2 in the accompanying LCO, correspond to ambient conditions of the valve at nominal operating temperature and pressure.
This LCO provides assurance that the MSSVs will perform their designed safety function to mitigate the consequences of accidents that could result in a challenge to the RCPB.
APPLICABILITY In MODES 1 and 2, a minimum of six MSSVs per steam generator are required to be OPERABLE (up to four allowed inoperable),
according to Table 3.7.1-1 in the accompanying LCO. which is limiting and bounds all lower MODES.
In MODE 3, a minimum of two MSSVs per steam generator are required to be operable (up to eight allowed inoperable) according to Table 3.7.1-1 in the accompanying LCO.
In MODES 4 and 5, there are no credible transients requiring the MSSVs.
The steam generators are not normally used for heat removal in MODES 5 and 6, and thus cannot be overpressurized; there is no requirement for the MSSVs to be OPERABLE in these MODES.
ACTIONS The ACTIONS table is modified by a Note indicating that separate Condition entry is allowed for each MSSV, A.1 and A.2 When 10 MSSVs are OPERABLE per steam generator (none inoperable), THERMAL POWER is limited to 100% RTP per the Operating Licenses, and the VOPT allowable trip setpoint is limited to 111.0% RTP per TS Table 3.3.1-1.
When one to four MSSVs per steam generator are inoperable in MODES 1 or 2, an alternative to restoring inoperable (continued)
PALO VERDE UNITS 1,2,3 B3.7.1-3 REVISION 34
BASES MSSVs B 3.7.1 ACTIONS (continued)
DJ.
When more than eight required MSSVs per steam generator are inoperable, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE REQUIREMENTS SR 3.7.1.1 This SR verifies the OPERABILITY of the MSSVs by the verification of each MSSV lift setpoints in accordance with the The ASME OM Code (Ref. 4), requires the following tests for MSSVs:
- a.
Visual examination;
- b.
Seat tightness determination;
- c.
Setpoint pressure determination (lift setting);
- d.
Compliance with owner's seat tightness criteria; and
- e.
Verification of the balancing device integrity on balanced valves.
The ASME OM Code requires that all valves be tested every 5 years, and a minimum of 20% of the valves tested every 24 months. The ASME OM Code specifies the activities and frequencies necessary to satisfy the requirements. Table 3.7.1-2 allows a +/- 3% setpoint tolerance for OPERABILITY; however, the valves are reset to +/- 1% during the Surveillance to allow for drift.
PALOVERDE UNITS 1,2,3 B3.7.1-5 REVISION §4
MSIVs B 3.7.2 BASES (continued)
ACTIONS (continued)
H.1 and H.2 (continued)
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 allowed in Condition F.
Inoperable MSIVs that cannot be restored to OPERABLE status within the specified Completion Time, but are closed, 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 7 day Completion Time is reasonable, based on engineering judgment, MSIV status indications available in the control room, and other administrative controls, to ensure these valves are in the closed position.
1.1 and I.2 If the MSIVs cannot be restored to OPERABLE status, or closed, within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2 conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE REQUIREMENTS SR 3.7.2.1 This SR verifies that the closure time of each MSIV is within the limit given in Reference 5 with each actuator train on an actual or simulated actuation signal and is within that assumed in the accident and containment analyses. This SR also verifies the Pfoefam INSERVICE TESTING PROGRAM. This SR is normally performed upon returning the unit to operation following a refueling outage. The MSIVs should not be full stroke tested at power.
Testina-Program INSERVICE TESTING PROGRAM. This Frequency demonstrates the valve closure time at least once per refueling cycle.
(continued)
PALO VERDE UNITS 1,2,3 B 3.7 2-8 REVISION §4
MFIVs B 3.7.3 BASES (continued)
SURVEILLANCE REQUIREMENTS SR 3.7.3.1 This SR verifies that closure time of each MFIV is within the limit given in Reference 2 on an actual or simulated actuation signal and is within that assumed in the accident and containment analyses. This SR also verifies the valve closure time is in TESTING PROGRAM. This SR is normally performed upon returning the unit to operation following a refueling outage. The MFIVs should not be full stroke tested at power.
INSERVICE TESTING PROGRAM. The Frequency for valve closure time is based on the refueling cycle. Operating experience has shown that these components usually pass the SR when performed at the specified Frequency.
REFERENCES 1.
UFSAR. Section 10.4.7.
- 2.
UFSAR, Section 5.1.5.
PALO VERDE UNITS 1,2,3 B 3.7.3-5 REVISION §4
AFW System B 3.7.5 BASES SURVEILLANCE REQUIREMENTS SR 3.7.5.2 (continued) normal tests of pump performance required by the ASME OM Code (Ref. 2). Because it is undesirable to introduce cold AFW into the steam generators while they are operating, this testing may be performed on recirculation flow. This test confirms one point on the pump design curve and can be indicative of overall performance. Such inservice tests confirm component OPERABILITY, trend performance, and detect incipient failures by indicating abnormal performance. Performance of inservice testing, discussed in the ASME OM Code, (Ref. 2). and the INSERVICE TESTING PROGRAM at 3 month inter-vate-satisfies this requirement.
This SR is modified by a Note indicating that the SR should be deferred until suitable test conditions are established. Normal operating pressure is established in the steam generators when RCS temperature reaches 532°F, this corresponds to a P^a, of 900 psia. This deferral is required because there is an insufficient steam pressure to perform the test.
SR 3.7.S.3 This SR ensures that AFW can be delivered to the appropriate steam generator, in the event of any accident or transient that generates an AFAS signal, by demonstrating that each automatic valve in the flow path actuates to its correct position on an actual or simulated actuation signal. This Surveillance is not required for valves that are locked, sealed, or othen/vise secured in the required position under administrative controls. This SR is not required for the non-essential train since there are no automatic valves which receive an AFAS. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
This SR is modified by a Note indicating that the SR should be deferred until suitable test conditions have been established.
Normal operating pressure is established in the steam generators when RCS temperature reaches 532°F, this corresponds to a P^g^
of 900 psia. This deferral is required because there is an insufficient steam pressure to perform the test.
(continued)
PALO VERDE UNITS 1,2,3 B 3.7.5-9 REVISION m