ML12353A158

Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications

ML12353A158
Person / Time
Site:	Palo Verde
Issue date:	12/12/2012
From:	Mims D Arizona Public Service Co, Pinnacle West Capital Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-06632-DCM/RKR/CJS
Download: ML12353A158 (33)

Text

10 CFR 50.90

• A MA subsidiary of Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Sr. Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Nuclear Regulatory and Oversight Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06632-DCM/RKR/CJS December 12, 2012 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, Maryland 20852

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Arizona Public Service Company (APS) is submitting a license amendment request (LAR) to change the Technical Specifications (TS) for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3. The proposed changes would replace the current PVNGS TS 3.4.17 limit on Reactor Coolant System (RCS) gross specific activity with a new limit on RCS noble gas specific activity. The noble gas specific activity limit would be based on a new Dose Equivalent Xe-1 33 (DEX) definition that would replace the current E-Bar, Average Disintegration Energy definition.

The changes are consistent with NRC approved Industry Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications, except as described in Enclosure 1. The availability of this TS improvement was announced in the Federal Register (FR) on March 19, 2007 (72 FR 12838) as part of the Consolidated Line Item Improvement Process (CLIIP).

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon

• Palo Verde 0 San Onofre

• South Texas 0 Wolf Creek

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications Page 2 provides a description and assessment of the proposed changes, as well as confirmation of applicability of the model safety evaluation to PVNGS. Enclosure 2 provides the existing TS and TS Bases pages marked-up to show the proposed changes. Enclosure 3 provides final TS pages.

APS requests approval of the proposed license amendment within one year of the date of this letter, with the amendment being implemented within 180 days of issuance. This letter contains no regulatory commitments.

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

Should you need further information regarding this amendment request, please contact Robert K. Roehler, Licensing Section Leader, at (623) 393-5241.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on .I4&(,4,) ,'/,*,

(Date)

Sincerely, DCM/RKR/CJS/hsc

Enclosures:

1. Description and Assessment of Proposed Changes

2. Proposed Technical Specification Changes and Technical Specification Bases Changes (Markups)

3. Final Technical Specification Pages (Retyped) cc: E. E. Collins Jr. NRC Region IV Regional Administrator L. K. Gibson NRC NRR Project Manager M. A. Brown NRC Senior Resident Inspector for PVNGS A. V. Godwin Arizona Radiation Regulatory Agency (ARRA)

T. Morales Arizona Radiation Regulatory Agency (ARRA)

Enclosure 1 Description and Assessment of Proposed Changes

Subject:

Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY SAFETY ANALYSIS 6.0 NO SIGNIFICANT HAZARDS CONSIDERATION

8.0 REFERENCES

1

Enclosure 1 License Amendment Request for Adoption of TSTF-490

1.0 DESCRIPTION

This letter is a request to amend the Renewed Operating Licenses NPF-41, NPF-51, and NPF-74 for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3.

The proposed changes would replace the current limits on primary coolant gross specific activity with limits on primary coolant noble gas activity. The noble gas activity would be based on DOSE EQUIVALENT XE-133 (DEX) and would take into account only the noble gas activity in the primary coolant. The changes were approved by the NRC staff Model Safety Evaluation (SE) dated March 19, 2007 (72 FR 12838)

(Reference 1). Technical Specification Task Force (TSTF) change traveler TSTF-490, Revision 0, Deletion of E-Bar Definition and Revision to RCS Specific Activity Technical Specifications, was announced for availability in the Federal Register on March 19, 2007 as part of the Consolidated Line Item Improvement Process (CLIIP). By memorandum from the Chief, Licensing Processes Branch, to the Plant Licensing Branch Chiefs, dated March 14, 2012, the NRC staff indicated that license amendment requests (LAR) related to TSTF-490 can be accepted for review, but will be handled through the normal LAR review process, instead of the expedited 6 month CLIIP schedule. Arizona Public Service Company (APS) is taking six clarifying deviations from the model application published in the Federal Register. The deviations are discussed in Section 2.0.

2.0 PROPOSED CHANGE

S Consistent with NRC-approved TSTF-490, Revision 0, the proposed TS changes:

• Revise the definition of DOSE EQUIVALENT 1-131.

• Delete the definition of E-Bar, AVERAGE DISINTEGRATION ENERGY.

0 Add a new TS definition for DOSE EQUIVALENT XE-1 33.

• Revise Limiting Condition for Operation (LCO) 3.4.17, "RCS Specific Activity" to delete references to gross specific activity; add limits for DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-1 33; and delete Figure 3.4.17-1, "Reactor Coolant DOSE EQUIVALENT 1-131 Specific Activity Limit versus Percent of RATED THERMAL POWER."

• Revise LCO 3.4.17, "Applicability" to specify the LCO is applicable in MODES 1, 2, 3, and 4.

Modify LCO 3.4.17 ACTIONS Table as follows:

2

Enclosure 1 License Amendment Request for Adoption of TSTF-490 A. Condition A is modified to delete the reference to Figure 3.4.17-1, and define an upper limit that is applicable at all power levels.

B. NUREG-1432 ACTIONS are reordered, moving Condition C to Condition B to be consistent with the Writer's Guide.

C. Condition B (was Condition C in NUREG-1432) is modified to provide a Condition and Required Action for DOSE EQUIVALENT XE-133 instead of gross specific activity. The Completion Time is changed from 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. A Note allowing the applicability of LCO 3.0.4.c is added, consistent with the Note to Required Action A. 1.

D. Condition C (was Condition B in NUREG-1432) is modified based on the changes to Conditions A and B and to reflect the change in the LCO Applicability.

0 Revise Surveillance Requirement (SR) 3.4.17.1 to verify the limit for DOSE EQUIVALENT XE-1 33.

Delete SR 3.4.17.3.

The following clarifying deviations from the model application published in the FR notice, and TSTF-490, are being made to address NRC requests for additional information sent to licensees who have adopted TSTF-490 and to reflect the PVNGS current licensing basis:

1) The definition for Dose Equivalent 1-131 (DEI) is being revised to specifically define the source document used for the thyroid dose conversion factors, rather than the multiple permissible source documents included in the TSTF definition. This is to be consistent with the PVNGS licensing basis and to address precedents from other licensees that have adopted the TSTF. Also, the DEI definition now includes the protocol that if a specific iodine isotope is not detected it will be assumed to be at the minimum detectable activity.

This was added to the DEI definition for consistency with the DEX definition, and is conservative.

2) References to the NRC staff Safety Evaluation (SE), dated September 27, 2006 (ADAMS ML062700612), are changed to refer to the NRC staff Safety Evaluation (SE), dated March 19, 2007 (72 FR 12838), because the SE dated September 27, 2006, that is referred to in the model application, is not publically available; whereas, the SE posted in the Federal Register on March 19, 2007 is publically available and approved for use.

3

Enclosure 1 License Amendment Request for Adoption of TSTF-490

3) The Steam Generator Tube Rupture (STGR) accident analysis, with a loss of off-site power and a single failure of an atmospheric dump valve (ADV) to close, is the most limiting accident for TS Limiting Condition for Operation (LCO) 3.4.17 and as such, references to a Steam Line Break (SLB) accident are not included in the proposed Bases for TS 3.4.17.

4) The TS Bases for TS 3.4.17 does not reference the Standard Review Plan (SRP) as described in TSTF-490 because the NRC has previously approved the use of 10 CFR Part 100 guideline values at PVNGS for the limiting SGTR event, with a loss of off-site power and a single failure of an ADV to close, instead of the limits listed in the SRP. NRC approval for the SRP deviation is documented in NUREG-0857, Safety Evaluation Report Related to the Operation of the Palo Verde Nuclear GeneratingStation, Units 1, 2, and 3, Supplement 7, dated December 1984, and re-affirmed in License Amendment No. 186, dated July 28, 2011. The conforming alterations were made in the TS Bases to be consistent with the PVNGS licensing basis, including the description of the limiting SGTR event.

5) The note "Only required to be performed in MODE 1"will be removed from Surveillance Requirement (SR) 3.4.17.2 and will not be added to SR 3.4.17.1, consistent with other licensees that have adopted TSTF-490.

6) The current PVNGS Technical Specifications have incorporated TSTF-425, Relocate Surveillance Frequencies to Licensee Control-RITSTF Initiative 5b, issued in Amendment No. 188 on December 15, 2011 (ADAMS Accession No. ML112620293). This amendment included relocation of the surveillance frequencies of 7 days for SR 3.4.17.1 and 14 days for SR 3.4.17.2 to the Surveillance Frequency Control Program required by TS 5.5.18. The proposed pages reflect the current use of the Surveillance Frequency Control Program instead of the frequency values reflected in the TSTF-490 markup pages.

3.0 BACKGROUND

The background for this application is as stated in the model SE in the NRC Notice of Availability published on March 19, 2007 (72 FR 12838), the NRC Notice for Comment published on November 20, 2006 (71 FR 67170,', and TSTF-490, Revision 0.

4.0 TECHNICAL ANALYSIS

APS has reviewed References 1 and 2. APS has applied the methodology in Reference 1 to develop the proposed TS changes. APS has also concluded that the justifications presented in TSTF-490, Revision 0, and the model SE prepared by the 4

Enclosure 1 License Amendment Request for Adoption of TSTF-490 NRC staff are applicable to Palo Verde Units 1, 2, and 3, and justify this amendment for the incorporation of the changes to the Palo Verde TS.

APS has also reviewed requests by the NRC staff for additional information from licensees that have adopted TSTF-490. To assist in the NRC staff review of this amendment request, the inputs for determining the Dose Equivalent lodine-131 and Xe-133 limit are summarized in the following tables.'

Dose Equivalent Iodine-131 Calculation 1-131 Dose Equivalent Activity Nuclide 1% Failed Fuel ICRP-30)1 Equivalence Factors for 1% Failed Fuel pCi/gm Sv/Bq DEF = DCFnuclide/DCFI-131 pCi/gm 1-131 3.00 2.92E-07 1.OOOE+00 3.OOE+00 1-132 0.83 1.74E-09 5.959E-03 4.94E-03 1-133 4.40 4.86E-08 1.664E-01 5.12E-01 1-134 0.52 2.88E-10 9.863E-04 5.13E-04 1-135 2.50 8.46E-09 2.897E-02 7.24E-02 Total Dose Equivalent 1-131 3.81 (1) Thyroid dose conversion factors from ICRP-30, 1979, Supplement to Part 1, pages 192-212, Table title, "Committed Dose Equivalent in Target Organs or Tissues per intake of Unit Activity" Dose Equivalent Xenon-133 Calculation RG 1.109 Xe-133 Dose Equivalent Activity Nuclide 1% Failed Fuel DCF (2) Equivalence Factors for 1% Failed Fuel pCi/gm mR-M 3/pCi-Yr DEF = DCFnnuCide/DCFxe'1 33 pCi/gm Kr-85 6.10 1.61 E-05 0.05 0.33 Kr-85M 1.30 1.17E-03 3.98 5.17 Kr-87 1.00 5.92E-03 20.14 20.14 Kr-88 2.80 1.47E-02 50.00 140.00 Xe-131M 5.90 9.15E-05 0.31 1.84 Xe-133M 0.34 2.51 E-04 0.85 0.29 Xe-1 33 360.00 2.94E-04 1.00 360.00 Xe-135M 0.74 3.12E-03 10.61 7.86 Xe-135 7.70 1.81 E-03 6.16 47.41 Xe-138 0.63 8.83E-03 30.03 18.92 Total Dose Equivalent Xe-133 602 (2) Dose Conveision Factors (DCF) for Whole Body; Regulatory Guide 1.109, Rev 1, Page 21, Table B-1 The DEI and DEX TS limits of 1.0 pCi/gm and 550 pCi/gm are conservative. The TS limits provide margin between where action would be required and the calculated results for DEI and DEX for the site, based on 1% failed fuel. The proposed DEX limit provides sufficient margin to accommodate the exclusion of those isotopes based on low concentration, short half life, or small dose conversion factors.

5

Enclosure 1 License Amendment Request for Adoption of TSTF-490

5.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on March 19, 2007 (72 FR 12838), the NRC Notice for Comment published on November 20, 2006 (71 FR 67170), and TSTF-490, Revision 0.

6.0 NO SIGNIFICANT HAZARDS CONSIDERATION APS has reviewed the proposed no significant hazards consideration determination published in the Federal Register on March 19, 2007 (72 FR 12838) as part of the CLIIP. APS has concluded that the proposed determination presented in the notice is applicable to Palo Verde and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).

7.0 ENVIRONMENTAL EVALUATION APS has reviewed the environmental consideration included in the model SE published in the Federal Register on March 19, 2007 (72 FR 12838) as part of the CLIIP. APS has concluded that the staff's findings presented therein are applicable to Palo Verde and the determination is hereby incorporated by reference for this application.

8.0 REFERENCES

1. Federal Notice of Availability published on March 19, 2007 (72 FR 12838).

2. Federal Notice for Comment published on November 20, 2006 (71 FR 67170).

6

Enclosure 2 Proposed Technical Specification Changes and Technical Specification Bases Changes (Markups)

TS Pages 1.1-3 1.1-3a 3.4.17-1 3.4.17-2 3.4.17-3 3.4.17-4 TS Bases Pages B 3.4.17-1 B 3.4.17-1a B 3.4.17-2 B 3.4.17-2a B 3.4.17-3 B 3.4.17-3a B 3.4.17-4 B 3.4.17-4a B 3.4.17-5 B 3.4.17-5a B 3.4.17-6

Definitions 1.1 1.1 Definitions (continued)

CORE ALTERATION CORE ALTERATION shall be the movement or manipulation of any fuel, sources, or reactivity control components [excluding control element assemblies (CEAs) withdrawn into the upper guide structure], within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose when inhaled as the combined activities of iodine isotopes *q...tiIty

@nd isotopic mixtuYvr of. 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. If a specific iodine isotope is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT I-131 shall be performed using The thyroid dose conversion factors used for this calculation shall be those listed in ICRP 30, 1979, Supplement to Part 1, page 192-212, Table--tited, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133. Xe-135m, Xe-135. and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity.

The determination of DOSE EQUIVALENT XE-133 shall (continued) 1.1-3 AMENDMENT NO. 44-ý I PALO VERDE UNITS 1,2,3

Definitions 1.1 be performed using effective dose conversion factors for air submersion listed in Table B-1 of Regulatory Guide 1.109, Rev. 1, NRC, 1977.

F AVFRQACM E shall be the average (weighted inprpor9tion DISINTEGRATION ENERGY to the concentration of each radionu-cide in the reactor coolant at the time of sampling) of the Sum, of the average beta and gamma energies per integration (in MeV) for is*t.pes. other than iodines, With half lives 15 minutes, making up at least 95% of the total noniodine activity in throlnt (continued)

1. 1-3a AMENDMENT NO. ;44 I PALO VERDE UNITS 1,2,3

RCS Specific Activity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Specific Activity LCO 3.4.17 The spe.ific activity of the reactor cool9nt RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY: MODES 1, a4 2, 3, and 4 MODE 3 ih RCS cold leg temperature T4ŽO--.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 ------------ NOTE--------

> l.n pCie, not LCO 3.0.4.c is applicable.

within limit.

A.1 Verify DOSE Once per EQUIVALENT 1-131 wi4hin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the acceptable region of Figure 3+71 : 60 pCi/gm.

AND A.2 Restore DOSE EQUIVALENT 1-131 to within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit.

NOTE---------

B. DOSE EQUIVALENT XE- LCO 3.0.4.c is applicable.

133 not within limit.

B.1 Restore DOSE EQUIVALENT 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> XE-133 to within limit.

(continued)

PALO VERDE UNITS 1,2,3 3.4.17-1 AMENDMENT NO. ý44, 445

RCS Specific Activity 3.4.17 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C9. Required Action C9.1 Be in MODE 3-wi-th 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and associated -

Completion Time of Condition A or B -not AND met.

OR DOSE EQUIVALENT 1-131 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

> 60 pCi /gm-i- the C.2 Be in MODE 5.

unacceptable region Figure 3.4417 1.

CGrss specific.1 Perform SR 34.1;.2. 4-houps1 ac-tivity of the A49 reactor cooant84 no-t wi th inA li Mit .

C.? Be in MODE 3 With ~ h9HPS2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify reactor coolant gress -er....ir-activity *!O 1 0/-E--fCig DOSE In accordance with EQUIVALENT XE-133 specific activity - the Surveillance 550 pCi/gm. Frequency Control Program (continued)

I PALO VERDE UNITS 1,2,3 3.4.17-2 AMENDMENT NO. 99

RCS Specific Activity 3.4.17 SURVEILLANCE REQUIREMENTS (continued)

SIIQ\F TI I ANICF FRF0i WIF41

~1-SR 3.4.17.2 Verify reactor coolant DOSE NOTE EQUIVALENT 1-131 specific activity Only r...ui ed to 5 1.0 pCi/gm. beperformedin!

MANE i1 In accordance with the Surveillance Frequency Control Program AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after THERMAL POWER change of Ž 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period Pe~ter-FRTe-- from. a sample taken4inHI accor-dance with MODE 1 aftcr a iiu ef 2 EFPDan the Surcveillance 20 days o~f MODE 1 operation have Fr~gequcnY ControlA elapsed sin-e- the rleactor was l-Astpeqa subritcalfor Q 48 hou~rs.

PALO VERDE UNITS 1,2,3 3.4.17-3 AMENDMENT NO. 4799

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RCS Specific Activity B 3.4.17 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.17 RCS Specific Activity BASES BACKGROUND The Code of Federal Regulations, 10 C-FR 100 (Ref 1) specifies the maximum dose to thc wholc body, and the. th.. eid an individual at the site boudary can Freeivc for 2 heous duing an accidcnt. The limits on

.pc.ific activity ensure that the doses; are held to a small f*aetion of the 10 CeR 100 limits during analyzed at and atcidents.

The RCS spccific activity LCO limits the allewabic ownccntration levl o r-adionuclides in the reactor colant. The LCO limits are established to minmiDze the offsite radioactivity dose consequences in the event of a stcam gcncrator- tubc fuptur-e (SGTR) accident.

The Loses ntains specific acytivitdlimits for both DOSE EQUtiALENT 1131 and grCss specific activity. The allowable levcls are intended to limit thc 2 hour-dose at the sitc boundaf-' to a small fraction of the 10 CER 100 dose guideline limits. The limits in the LCO are standarized based oni parametriceli of ofsite radiactivity dose consequences fore trpial site locatiens.

The parametriE evaluatiEns showcd the potential offbsite dse levels for an SGTeR accident were an apfpfr iately soall froation of the 10 CthR 100 dose guideline limits. Each evaluation assumes a broad range of site applicable atmospher-ic disper-sion factors in at parametdci evaluation.

The maximum dose that an individual at the exclusion area boundary can receive for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following an accident, or at the low population zone outer boundary for the radiological release duration, is specified in 10 CER 100.11 (Ref. 1). Doses to control room operators must be limited pe GDC 19. The limits on specific activity ensure that the offsite and control room doses are appropriately limited during analyzed transients and accidents.

The RCS specific activity LCO limits the allowable concentration level of radionuclides in the reactor coolant. The LCO limits are established to minimize the dose consequences in the event of a steam generator tube rupture (SGTR) accident.

The LCO contains specific activity limits for both DOSE EOUIVALENT 1-131 and DOSE EOUIVALENT XE- 133. The allowable levels are intended to ensure that offsite and control room doses meet the 10 CFR 100. 11 (Ref. 1) and GDC 19 limits respectively.

(continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-1 REVISION 0

RCS Specific Activity B 3.4.17 APPLICABLE The LCO limits on the specific activit-y of the react SAFETY ANALYSES coola-nt en.sur.e that the r.esulting 2 hour-doses at the ssite b;euif..nda-y will not excced a small fraction ef the 10 CFR 100 dose guidelinie limits following an SGT-R accident. The SGTR safety analysis (Ref. 2) assumes the specific activity of the reacto* coolant at the LCO limits and an cxisting reactor.colant steam generator. (SG) tube lcakage. rate

.m.ef 1 The analysis for-the SGT-R accident establishes the acceptance limits for RCS specific acativity. Refer-ence to (continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-1 a REVISION 0

RCS Specific Activity B 3.4.17 BASES APPLICABLE this analysis is used t. assess changes to the fa.ility that SAFETY ANALYSES could affect RCS specific activity as they r.elate to th (continued) aeeeptaneeliis.

The rise in p-ressure in th6 ptur.d SG.auses radioactively contaminated steam todishag_thc to atmosphere thr-ough the atmospher-c du~mp valvCs or the main steam safety valves. The atmospherico discharge steps when the turbine bypass to the condenser rmeves the e1cess CeFRgy to rapidly r1educe the RS pressure and clase the valves. The unaffected SG raemyves oefre decay heat by venting steam until the ecldown ends.

The safety analysis shows the readioloc colt tnsequences of an SGTu laccdet arae within5a small fractien of the RefxrtenTe 1 dose guideline limits.

Operation with iodine specific activity levels grseatr thalni the LiO li.it is pecmissiblc if the activity levels do net exceed the limits shown in Figrhe 3.4.17 1 for more than 1c8 hoeutrs. The above limit perissible iodine levels shown in Figure 3.4.17 1 are acceptable because of the lov.

time limit. The allowable limits shown on Figure 3.4.17 1accommodate possible iodine spiking phenomenon which may occure folwingechanges in hefmalpower, RCS specific activity satisfies Cr-iter-ion 2 of 10 CFR 50.36 (c)(2)(ii).

The LCO limits on the specific activity of the reactor coolant ensure that the resulting offsite and control room doses meet the 10 CFR 100. 11 (Ref. 1) and GDC 19 limits following a SGTR accident. The safet analysis (Ref. 2) assumes the specific activicy of the reactor coolant is at the LCO limits, and an existing reactor coolant steam generator (SG) tube leakage rate of 0.5 gpm per steam generator exists. The safety analysis assumes the specific activity of the secondary coolant is at its limit of 0.1 UCi/VAm DOSE EQUiVALENT 1-131 from LCO 3.7.16. "Secondary Specific Activity."

The analysis for a SGTR accident establishes the acceptance limits for RCS specific activity. Reference to this analysis is used to assess changes to the unit that could affect RCS specific activity, as they relate to the acceptance limits.

The safety analysis considers two cases of reactor coolant iodine specific activity. One case assumes specific activity at 1.0 iiCi/gm DOSE EQUIVALENT 1-131 with a concurrent large iodine spike that increases the rate of release of iodine from the fuel rods containing, cladding defects to the primary coolant immediately after a SGTR (by a factor of 335).

The second case assumes the initial reactor coolant iodine activity at 60.0 (continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-2 REVISION 2-7

RCS Specific Activity B 3.4.17 BASES uCi/gm DOSE EQUIVALENT 1-131 due to an iodine spike caused by a reactor or an RCS transient prior to the accident. In both cases, the noble gas specific activity is assumed to be 550 iiCi/grn DOSE EQUIVALENT XE-133.

The STGR analysis assumes a rise in pressure in the ruptured SG causes radioactively contaminated steam to discharge to the atmosphere through the atmospheric dump valves or the main steam safety valves. The atmospheric discharge continues through an assumed stuck open atmospheric dump valve. The unaffected SG removes core decay heat by venting steam until the cooldown event ends and the Shutdown Cooling (SDC) system is placed in service.

Operation with iodine specific activity levels greater than the LCO limit is permissible, if the activity levels do not exceed 60.0 mCi/gm for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

The limits on RCS specific activity are also used for establishing standardization in radiation shielding and plant personnel radiation protection practices.

RCS snecific activity satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).

LCO The specifi, iodine activity is limited to 1.0 #1Cigm DOSE EQUt.'ALENT 1 13 1, and the g.oss speeific aetivi-,y in the pr.ima*,

eoolant is limited to the number-of pjiW Iqa

t. 1-00 divided by-t (average disintegration en"er-gy of the sum... of t.arge..bta and gamma ener-gies of the coolant nuclides). The limit An DOSE EQUIVT ALENT I 131 ensur-es th-2 hour-th)T-eid dose to an individual at the site betmdafý, during the Design Bas is AeCcid-enat (PBA) wil be aRssm-all fraction of the allowed th)49id dose.

The limit on--gross specific activity ensures the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> whole body dose to an inidividual at#_ the, Site.boundar-y dur-ing the DBA will be a small fraction

_r4- ýll .... A,,K 1 1, A ,. A -

-" VlJ~Llty Y Vos (continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-2a REVISION.1

RCS Specific Activity B 3.4.17 BASES LCO Thp F%.T-R As 2,ident analysis (Refl. 2) sh .. .. th.. .t th... . h...

(continued) site boundat=) dose levels arc within acceptable limnits. Violation of the LCO may resul1-1t in-; reactor0f coolant r-adioactivity level-s th-at coeuld, in the event of an SGT.R, lead to site boundary doses that ex"eed the 10 CFR 100 dose guideline limnits.

The iodine specific activity in the reactor coolant is limited to 1.0 RCi/gm DOSE EQUIVALENT 1-131, and the noble gas specific activity in the reactor coolant is limited to 550 itCi/grm DOSE EQUIVALENT XE-133.

The limits on specific activity ensure that offsite and control room doses will meet the 10 CFR 100.11 (Ref. 1) and GDC 19 limits.

The SGTR accident analysis (Ref. 2) shows that the calculated doses are within acceptable limits. Violation of the LCO may result in reactor coolant radioactivity levels that could, in the event of a SGTR, lead to doses that exceed the 10 CFR 100.11 (Ref. 1) and GDC 19 limits.

APPLICABILITY 14MO 4DES 1 and 2, and in MOhDE"3 with RCS.-- cold leg tempera 500nF, operation within the LCO limits for DOSE EQUIVALENT 1131 andEgross ific activiT is necessaohe- Potential e tconsequences of a SGTR to withinthee aceptable site boundaC' dose al1ues.

For operSatin in MODE 3 with RaS orld leg temperiaturs fe 5O2, and in MO0DES 4 and 5, the release of radioactivity in the event of an SGTR is unllikely since the satur-atio prsur fthe r---Aeato coo eelant is below~ the lift pressure sCfings of the atmespheraie dump valves and main steam In MODES 1,2. 3, and 4.moeration within the LCO limits for DOSE EUtVALENT 1-13r1 and DOSE EQUIVALENT XE-133 is necessary to limit the potential consequences of a SGTR to within the 10 CFR 100.11 (Ref. 1) and GDC 19 limits.

In MODES 5 and 6. the steam generators are not beingz used for decay heat removal, the RCS and steam ggenerators are depressurized. and p2rimary to secondary leakage is minimal. Therefore, the monitoring of RCS specific activity is not required.

(continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-3 REVISION 4-2

RCS Specific Activity B 3.4.17 BASES ACTIONS A. 1 and A.2 With the DOSE EQUIVALENT 1-131 greater than the LCO limit, samples at intervals of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must be taken to demonstrate the limits of Figure 3.4.17 1 are net exceeded that the specific activity is < 60.0 LRCi/gr. The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is required to obtain and analyze a sample.

Sampling is continued every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to provide a trend must continue for tfending.

TheDOEThe DOSE EQUIVALENT 1131Imu-tb r- red to within withinlimits 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.

The Completion Time of 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> is required if the linit violation rexputed from ni l itdinwe spioineng.

A Note permits the use ef the previsions of LCO 3.0.4.e. This allowance permits ent'Y into the applicable MODE(s) while relying on the ACTIONS.

The DOSE EQUIVALENT 1-131 must be restored to within limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable since it is expected that, if there were an iodine spike, the normal coolant iodine concentration would be restored within this time period. Also, there is a low probability of a SGTR occurring during this time period..

A Note permits the use of the provisions of LCO 3.0.4.c. This allowance permits entry into the applicable MODE(S). relying on Reqiuired Actions A.lI and A.2 while the DOSE EQUIVALENT 1-13 1 [CO limit is not met. This allowance is acceptable due to the sigznificant conservatism incorporated into the specific activity limit, the low probability of an event which is limiting due to exceeding this limit, and the ability to restore transient-specific activity excursions while the plant remains at, or proceeds to, power operation.

(continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-3a REVISION 42-

RCS Specific Activity B 3.4.17 BASES ACTIONS A. 1 and A.2 (continued)

This allwanc able due to the sienificant c rv teatism incor-porated into the specific activity limnit, the low probabilivy, of an event whieh is limiting due to cxcccding this lim.it, and the ability to ester-e transient spccifie activity excuirsions while the plant remains at-, o prOceeds to power-operation.

B.1 if a Requir~ed Action and associated Completion Time of Condition A is not met or if the DOSE EQUIVALENT X131 is in the unaLCeptabl region of Figure 3.4.17 1, the react1r must be brought to MODE 3 with RCS eold leg temper-a~r- < 5000 F-within 6 houirs. The allowed Completion Time of 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reqied to r-each MODE 3 below 500'F-w~ithout c-hallenging plant systems.

With the DOSE EQUIVALENT XE- 13 3 greater than the LCO limit.

DOSE EQUIVALENT XE- 13 3 must be restored to within limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The allowed Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is acceptable since it is expected that, if there were a noble gas spike, the normal coolant noble gas concentration would be restored within this time period. Also, there is a low probabilitv of a SGTR occurring during this time neriod.

A Note permits the use of the provisions of LCO 3.0.4.c. This allowance permits entry into the applicable MODE(S), relying on Required Action B.l while the DOSE EQUIVALENT XE-133 LCO limit is not met. This allowance is acceptable due to the significant conservatism incorporated into the specific activity limit, the low probability of an event which is limiting due to exceeding this limit, and the ability to restore transient-specific activity excursions while the plant remains at, or proceeds to, power operation.

C.lI and C.2 With the gross specific aetivity in excess of the allowed limit, an analysis must be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to dett rminte DOSE EQUIVALENT I

-- - . - M OMB et OR MR- A-- . -1,91-gs S required to obtain and analy-ze -a sample.

The change within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to MO0DE 3 and RCS cold leg temper-aur-e <

letheiat pressure ofthe reacto olant below the setpeints of the main steamn safety valves and minimizes the potential for (continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-4 REVISION 4 RCS Specific Activity B 3.4.17 BASES venting the SG to the envir-enment in an SGT-R event. The allowed Completion Time of 6 heur-s is r-gureut rtcii TV F; :3 belew 5u' 0rtu ~lpw~ uuto~

and without challenging plant systems, If the Required Action and associated Completion Time of Condition A or B is not met, or if the DOSE EQUIVALENT 1-131 is > 60.0 gCi/am, the reactor must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 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 plant conditions from full power conditions in an orderly manner and without challenging plant systems.

(continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-4a REVISION 42-

RCS Specific Activity B 3.4.17 BASES (continued)

SURVEILLANCE SR 3.4.17.1 REQUIREMENTS SR 3.4.17.1 requires performing a gamma isotopic analysis as a measure of the noble gas specific activity of the reactor coolant. This measurement is the sum of the degassed gamma activities and the gaseous gamma activities in the sample taken. This Surveillance provides an indication of any increase in the noble gas specific activity.

Trending the results of this Surveillance allows proper remedial action to be taken before reaching the LCO limit under normal operating conditions.

The Surveillanerqie per-forming a gamma isotopic analysis as a mneasur-e-ot the goss specific activXiy cf the reactor-coolant. While basically a quniatvneasur-e of radionuelides A'with half liv'es longcr-than 1-5 mninutes,ThkSir.'i~anc excluidingnnvdcgnninicair iodines, this measuirement May is nccawin~ ~zxfi the sumf of the dcgassed gam aeiviies and the gaseous gamama activ'ities in the samaple taken.

activity. TrFending the results; ofthis ureilac allows proper-remedial acation to be taken before reaching the LCO limait un-de-r normf-Aaloprtn eonditions. The, Surveillance is applicable in MODES 1 and 2, and in MODE 3 with RCS cold leg temper-ature -atle-ast _5002F.

-The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

If a specific noble gas nuclide listed in the definition of DOSE EQUIVALENT XE-133 is not detected, it should be assumed to be present at the minimum detectable activity.

SR 3.4.17.2 This Surveillance is performed to ensure iodine specific activity remains within limit during normal operation and following fast power changes when fael-failke iodine spiking is more apt to occur. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.Te 4dysrviaae4qeeismdfebyteNe "Only required to be per-formed in MODE 1." This is acceptable because the. level of fison ..... et .....

ge.. -ate MODE 2_*,,,~and 3 is..... les than in MODE 1. The Frequency, between 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power change of Ž 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, is established because the iodine levels peak during this time following fidel--faile iodine spike initiation; samples at other times would provide inaccurate results.

(continued)

PALO VERDE UNITS 1,2,3 B 3.4.17-5 REVISION -- 56

RCS Specific Activity B 3.4.17 BASES (continued)

If a specific iodine isotope listed in the definition of DOSE EQUIVALENT 1-131 is not detected, it should be assumed to be present at the minimum detectable activity.

4 6

• 4 . *

• LI 4 . 4 1 I 4 4 One sample is sutticient it the plant has gone through a shudow or -f- the transient is complete in 6heufs.

SR 3.1.17.2 14 day Fr-equency is modified by a Note 'which requires the Sun'illnceto only be perfonned in MO0DE 1. This is requir-ed becauise the lcvel of fission products gcncratcd in other-MO0DES is mnuch less.

Als3 , fuel failuffre-s -associ-atedwith fast power-change imoeat to occur (continued)

I PALO VERDE UNITS 1,2,3 B 3.4.17-5a REVISION-5

RCS Specific Activity B 3.4.17 BASES OTTDXT rTT T A XT'*U SR 3.4.17.4 D1"TT-1"RUTS (continued) A r-adiochemficeal analysis for-= tEdretennmination is r~equirced with thc plant oper-ating in MO0DE 1 equilibr-iumf conditions. T-he #Fdetem~iiation dir-ectly relaters toe the LCO-. and is requir-ed to ved-if' plant oper-ation with nfl the specified gross acstivity LCO limnit. Theanlssfr-ia measurfement of the average -enriscr- disintegration for-isotopes 'with half lives longer-than 15 minutes, excludinig iodines. The Sur~eillance FrFequencey i-s con-molled- under- the Sur.'cillancee F-requency Conto Pr-egfafn.

This SR has been modificd by a Note that indicates sampling is requir-ed to be per-fonned 'within 31I days after- 2 effective ifull po'wer- days and 20 days of MO0DE 1 oper-ation havc clapsed since the r-eactor- was last subcritical for-

Ž 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> should the 181 day Frequency inte..'al be exceeded. Futher discussion of SR Note fot- at is found in Section 1.4, Fr-equency. This ensures the r-adioactive mnater-ials arc at equilibduitm so the anayss ortie r-epr-esentative and not skewed by a emud burst or-other-similar-abnonnfal event.

REFERENCES 1. 10 CFR 100.11,-4-97.

2. UFSAR, Section 15.6.3, PALO VERDE UNITS 1,2,3 B 3.4.17-6 REVISION -%I

Enclosure 3 Final Technical Specification Pages (Retyped) 1.1-3 1.1-4 1.1-5 1.1-6 3.4.17-1 3.4.17-2

Definitions 1.1 1.1 Definitions CORE ALTERATION CORE ALTERATION shall be the movement or manipulation of any fuel, sources, or reactivity control components [excluding control element assemblies (CEAs) withdrawn into the upper guide structure], within the reactor vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. If a specific iodine isotope is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT 1-131 shall be performed using ICRP-30, 1979, Supplement to Part 1, page 192-212, Table titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity.

The determination of DOSE EQUIVALENT XE-133 shall (continued)

PALO VERDE UNITS 1,2,3 1.1-3 AMENDMENT NO. 4-1-,

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.

Knlis 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 (continued)

PALO VERDE UNITS 1,2,3 1.1-4 AMENDMENT NO.

Definitions 1.1 1.1 Definitions LEAKAGE (continued) 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System (primary to secondary LEAKAGE).

b. Unidentified LEAKAGE All LEAKAGE that is not identified LEAKAGE:

c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.

MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, cold leg reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

NEUTRON RATED The indicated neutron flux at RTP.

THERMAL POWER (NRTP)

OPERABLE - OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the UFSAR; (continued)

PALO VERDE UNITS 1,2,3 1.1-5 AMENDMENT NO.4-647.

Definitions 1.1 1.1 Definitions PHYSICS TESTS b. Authorized under the provisions of (continued) 10 CFR 50.59: or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND The PTLR is the site specific document that TEMPERATURE LIMITS provides the reactor vessel pressure and REPORT (PTLR) temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.9.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3990 MWt.

REACTOR PROTECTIVE The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted. 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.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All full strength CEAs (shutdown and regulating) are fully inserted except for the single CEA of highest reactivity worth, which is assumed to be fully withdrawn. With any full strength CEAs not capable of being fully inserted, the withdrawn reactivity worth of these CEAs must be accounted for in the determination of SDM and

b. There is no change in part strength CEA position.

PALO VERDE UNITS 1,2,3 1.1-6 AMENDMENT NO. 4-7-9.

RCS Specific Activity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 RCS Specific Activity LCO 3.4.17 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT 1-131 ------------ NOTE---------

not within limit. LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per EQUIVALENT 1-131 ! 60 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> pCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 to within limit.

B. DOSE EQUIVALENT XE-133 not within ----------- NOTE--------

limit. LCO 3.0.4.c is applicable.

B.1 Restore DOSE EQUIVALENT 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> XE-133 to within limit.

(continued)

PALO VERDE UNITS 1,2,3 3.4.17-1 AMENDMENT NO. 4-W

RCS Specific Activity 3.4.17 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 of Condition AND A or B not met.

OR 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 /> DOSE EQUIVALENT 1-131

> 60 pCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify reactor coolant DOSE EQUIVALENT In accordance with XE-133 specific activity : 550 pCi/gm. the Surveillance Frequency Control Program SR 3.4.17.2 Verify reactor coolant DOSE In accordance with EQUIVALENT 1-131 specific activity the Surveillance 1.0 pCi/gm. Frequency Control Program AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after THERMAL POWER change of Ž 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period PALO VERDE UNITS 1,2,3 3.4.17-2 AMENDMENT NO. -ý99,