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{{#Wiki_filter:CATEGORY j.REGULA'1 Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)ACCESSION NBR:9801210044 DOC.DATE: 98/01/13 NOTARIZED:
{{#Wiki_filter:CATEGORY j.
NO DOCKET I FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-'50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFIL1ATION L'EVINE,J.M.
REGULA'1   Y INFORMATION DISTRIBUTIO           SYSTEM (RIDS)
Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk),c
ACCESSION NBR:9801210044           DOC.DATE:   98/01/13       NOTARIZED: NO           DOCKET   I FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-'50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME           AUTHOR AFFIL1ATION L'EVINE,J.M.         Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME           RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Informs that plant updating IST program to ASME Boiler 8~~Pressure Vessel Code,1989 Ed@tv.on.Updated program wall take A effect on 980115.T DTSTRTBUTTON CODE: A047D CORTES RECEIVED:LTR I ENCL I SLEE: 4-t TITLE: OR Submittal:
Informs that plant updating IST program to ASME Boiler 8                             ,c Pressure Vessel Code,1989 Ed@tv.on. Updated program wall take
Inservice/Testing/Relief from ASME Code-GL-89-04 E NOTES: STANDARDIZED PLANT Standardized plant.Standardized plant.05000528G 05000529 05000530p INTERNAL RECXPIENT ID CODE/NAME PD4-2 LA CLIFFORD,J E NUD B~gta-CT RES/DET/EXB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1'RECIPIENT ID CODE/NAME PD4-2 PD AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS2 RES/DET/EMMEB COPIES LTTR ENCL 1 1 1 1 1 1 1 0 1 1 D EXTERNAL: LITCO ANDERSON NRC PDR 1 1 1 1 NOAC E NOTE TO ALL"RIDS" RECIPIENTS:
                                                  ~  ~
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 L
A effect   on 980115.
cenmlbncnr.lematke,&erg'alo Verde Nuclear Generating Station James M.Levine Senior Vice President Nuclear TEL (602)3934300 FAX (602)3936077 Mail Station 7602 P.O.Box 62034 Phoenix, AZ 65072-2034 102-04060-JML/SAB/JRP January 13, 1998 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
4- t      T DTSTRTBUTTON CODE: A047D         CORTES RECEIVED:LTR         I   ENCL I   SLEE:
TITLE: OR   Submittal: Inservice/Testing/Relief           from ASME Code -     GL-89-04         E NOTES: STANDARDIZED PLANT                                                               05000528G Standardized plant.                                                               05000529 Standardized plant.                                                               05000530p RECXPIENT           COPIES              RECIPIENT            COPIES ID CODE/NAME         LTTR ENCL          ID  CODE/NAME        LTTR ENCL PD4-2 LA                   1     1       PD4-2 PD                  1     1 CLIFFORD,J                1     1 INTERNAL                              1     1     AEOD/SPD/RAB               1    1 E                    1  '  1      NRR/DE/EMEB               1    1 NUD B~gta-        CT      1              OGC/HDS2                 1    0 RES/DET/EXB                              RES/DET/EMMEB             1     1               D EXTERNAL: LITCO ANDERSON             1    1      NOAC NRC PDR                   1     1 E
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR               14   ENCL     13
 
L cenmlbncnr.lematke,
                        &erg'alo James M. Levine                   TEL (602)3934300           Mail Station 7602 Verde Nuclear                Senior Vice President            FAX (602)3936077           P.O. Box 62034 Generating Station                Nuclear                                                      Phoenix, AZ 65072-2034 102-04060 JML/SAB/JRP January 13, 1998 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001


==Dear Sirs:==
==Dear Sirs:==


==Subject:==
==Subject:==
Palo Verde Nuclear Generating Station (PVNGS)'nits 1,2, and 3 Docket Nos.STN 50-528/529/530 Inservice Testing (IST)Second 10 Year Program In accordance with 10 CFR 50.55a (f)(4)(ii), Palo Verde.is updating the IST Program to the American Society of Mechanical Engineers (ASME)Boiler and Pressure Vessel (B&PV)Code, 1989 Edition.The updated program complies with the requirements of the latest edition and addenda of the ASME B&PV Code incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval.Subsections IWP and IWV of the Code refer to implementing the requirements of ASME/American National Standards Institute (ANSI)OM-6 and OM-10, respectively.
Palo Verde Nuclear Generating Station (PVNGS) 1,2, and 3                                                     'nits Docket Nos. STN 50-528/529/530 Inservice Testing (IST) Second 10 Year Program In accordance with 10 CFR 50.55a (f)(4)(ii), Palo Verde. is updating the IST Program to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1989 Edition. The updated program complies with the requirements of the latest edition and addenda of the ASME B&PV Code incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval. Subsections IWP and IWV of the Code refer to implementing the requirements of ASME / American National Standards Institute (ANSI) OM-6 and OM-10, respectively. Therefore, the update to the IST Program is based on the applicable requirements set forth in ASME/ANSI OM-1987, "Operation and Maintenance of Nuclear Power Plants,"
Therefore, the update to the IST Program is based on the applicable requirements set forth in ASME/ANSI OM-1987,"Operation and Maintenance of Nuclear Power Plants," including the ASME/ANSI OMa-1988 Addenda.The updated program will take effect on January 15, 1998.Augmented Testing Consistent with the philosophy and recommendations of Section 2.2 of NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, Palo Verde has developed an augmented testing program for selected Non-IST components.
including the ASME/ANSI OMa-1988 Addenda. The updated program will take effect on January 15, 1998.
These components have been integrated into the tables in Attachment (1)for convenience.
Augmented Testing Consistent with the philosophy and recommendations of Section 2.2 of NUREG - 1482, Guidelines for Inservice Testing at Nuclear Power Plants, Palo Verde has developed an augmented testing program for selected Non-IST components. These components have been integrated into the tables in Attachment (1) for convenience. Palo Verde chose to include " cold shutdown/refueling justifications" and "relief requests" for these non-code components to maintain consistency and clearly identify the basis for any "deviations" from the code.
Palo Verde chose to include" cold shutdown/refueling justifications" and"relief requests" for these non-code components to maintain consistency and clearly identify the basis for any"deviations" from the code.980i2i0044, 980ii3 PDR ADQCK 05000528 P''PDR j , IIIIIIIIIIIIIIIIIIIIIIIII IIIIIIIIIII U I I I U.S.Nuclear Regulatory Commission Update to the Inservice Testing (IST)Program Page 2 Summary of Relief Requests Table 1 contains a list of relief requests that are being submitted for NRC review and approval.Several of the relief requests document situations where complying with Code requirements is impractical, and are submitted in accordance with 10CFR 50.55a(f)(5) and (6).PVNGS will implement the relief associated with"impractical" tests while the NRC is reviewing the relief requests, as provided for in Section 2.5 of NUREG-1482.PVNGS will not implement"proposed alternative" tests until use of the alternative is authorized by the NRC per 10CFR 50.55a(a)(3).
980i2i0044, 980ii3 PDR       ADQCK             05000528 P                             ''PDR j
Table 1 RR¹Description Impractical/
                                                            ,   IIIIIIIIIIIIIIIIIIIIIIIII IIIIIIIIIII
Alternative VRR-07 Containment Sump Check Valve Disassembly and Inspection Schedule VRR-08 PIV Closed Exercising Schedule PRR-03 Charging Pump Flow Rate Measurement PRR-07 Charging Pump Vibration Measurement PRR-08 Smooth-Running Pumps PRR-09 Evaluation as Corrective Action PRR-10 ANII Involvement in Pump Inservice Testing VRR-05 Downcomer Feedwater Check Valve Closed Exercising Impractical Impractical Proposed Alternative Proposed Alternative Proposed Alternative Impractical Proposed Alternative Impractical VRR-09 Verification of Thermal Equilibrium During Safety/Relief Valve Testing Proposed Alternative VRR-10 Accumulator Volume for Safety/Relief Valve Testing VRR-11 ANII Involvement in Valve Inservice Testing VRR-12 MOV Exercising and Stroke Timing VRR-1 3 Check Valve Condition Monitoring Proposed Alternative Proposed Alternative Proposed Alternative Proposed Alternative The remaining relief requests document other types of Code deviations or approaches, which do not require specific NRC review or approval.These relief requests can be grouped into three general groups, as described below:~Deviations associated with au mented tests.Augmented tests are those tests that are not required by the ASME Code but are voluntarily included in the PVNGS IST Program for convenience.
 
PVNGS policy is to perform augmented tests in accordance with the Code as far as practical.
U I
Deviations from Code requirements are documented as relief requests for consistency, but they do not require NRC approval because augmented tests are outside the scope of the IST Program.  
I I
 
U. S. Nuclear Regulatory Commission Update to the Inservice Testing (IST) Program Page 2 Summary of Relief Requests Table 1 contains a list of relief requests that are being submitted for NRC review and approval. Several of the relief requests document situations where complying with Code requirements is impractical, and are submitted in accordance with 10CFR 50.55a(f)(5) and (6). PVNGS will implement the relief associated with "impractical" tests while the NRC is reviewing the relief requests, as provided for in Section 2.5 of NUREG - 1482.
PVNGS will not implement "proposed alternative" tests until use of the alternative is authorized by the NRC per 10CFR 50.55a(a)(3).
Table 1 RR¹         Description                                               Impractical/
Alternative PRR-03     Charging Pump Flow Rate Measurement                       Impractical PRR-07     Charging Pump Vibration Measurement                       Impractical PRR-08     Smooth-Running Pumps                                       Proposed Alternative PRR-09     Evaluation as Corrective Action                           Proposed Alternative PRR-10     ANII Involvement in Pump Inservice Testing                 Proposed Alternative VRR-05     Downcomer Feedwater Check Valve Closed Exercising         Impractical VRR-07      Containment Sump Check Valve Disassembly and              Proposed Alternative Inspection Schedule VRR-08      PIV Closed Exercising Schedule                            Impractical VRR-09     Verification of Thermal Equilibrium During Safety/Relief   Proposed Alternative Valve Testing VRR-10     Accumulator Volume for Safety/Relief Valve Testing         Proposed  Alternative VRR-11     ANII Involvement in Valve Inservice Testing               Proposed  Alternative VRR-12     MOV Exercising and Stroke Timing                           Proposed  Alternative VRR-1 3     Check Valve Condition Monitoring                           Proposed Alternative The remaining relief requests document other types of Code deviations or approaches, which do not require specific NRC review or approval. These relief requests can be grouped into three general groups, as described below:
  ~   Deviations associated with au mented tests. Augmented tests are those tests that are not required by the ASME Code but are voluntarily included in the PVNGS IST Program for convenience.       PVNGS policy is to perform augmented tests in accordance with the Code as far as practical. Deviations from Code requirements are documented as relief requests for consistency, but they do not require NRC approval because augmented tests are outside the scope of the IST Program.


U.S.Nuclear Regulatory Commission Update to the Inservice Testing (IST)Program Page 3~A roaches allowed b NUREG-1482.
U. S. Nuclear Regulatory Commission Update to the Inservice Testing (IST) Program Page 3
NUREG-1482 describes several approaches to testing that have been found acceptable by the NRC if their use is documented in the IST Program.PVNGS has documented the use of these approaches in relief requests for convenience.
~   A     roaches   allowed   b     NUREG-1482. NUREG-1482 describes           several approaches to testing that have been found acceptable by the NRC if their use is documented in the IST Program.         PVNGS has documented the use of these approaches in relief requests for convenience. These relief requests do not require NRC review or approval because these approaches have already been found acceptable by the NRC.
These relief requests do not require NRC review or approval because these approaches have already been found acceptable by the NRC.~Alternative testin a roved b Generic Letter 89-04.Generic Letter 89-04 granted approval to implement the alternative testing delineated in Positions 1,2,6,7,9, and 10 of the generic letter provided their use is documented in the IST Program.Use of these positions is documented in Relief Requests for convenience.
~   Alternative testin     a roved b     Generic Letter 89-04. Generic Letter 89-04 granted approval to implement the alternative testing delineated in Positions 1,2,6,7,9, and 10 of the generic letter provided their use is documented in the IST Program. Use of these positions is documented in Relief Requests for convenience.
These relief requests do not require NRC review or approval because they follow the provisions of Generic Letter 89-04.The description of the relief requests described above are contained in Attachment 1.APS requests NRC review and approval of the relief requests listed in Table 1 above.Im lementation Strate All tests performed after the implementation date will be conducted in accordance with the updated IST Program.The implementation of the second 10 year IST Program will require the performance of a number of new surveillance requirements.
These relief requests do not require NRC review or approval because they follow the provisions of Generic Letter 89-04.
APS intends to treat these new requirements as being"met" at the time of implementation of the updated program.The first actual performance of the surveillance requirements will be scheduled within the specified frequency starting from the date of implementation.
The description of the relief requests described above are contained in Attachment 1.
For surveillance requirements whose frequency of performance is being extended or shortened, the due date for the next performance of the surveillance will be changed to reflect the new required frequency upon implementation.
APS requests NRC review and approval of the relief requests listed in Table 1 above.
Should you have any questions regarding this matter, please contact Scott A.Bauer at (602)393-5978.Sincerely, JML/SAB/JRP/rlh Enclosure  
Im lementation Strate All tests performed after the implementation date will be conducted in accordance with the updated IST Program. The implementation of the second 10 year IST Program will require the performance of a number of new surveillance requirements. APS intends to treat these new requirements as being "met" at the time of implementation of the updated program. The first actual performance of the surveillance requirements will be scheduled within the specified frequency starting from the date of implementation. For surveillance requirements whose frequency of performance is being extended or shortened, the due date for the next performance of the surveillance will be changed to reflect the new required frequency upon implementation.
Should you have any questions regarding this matter, please contact Scott A. Bauer at (602) 393- 5978.
Sincerely, JML/SAB/JRP/rlh Enclosure


U.S.Nuclear Regulatory Commission Update to the Inservice Testing (IST)Program Page 4 cc: E.W.Merschoff J.W.Clifford J.M.Moorman K.E.Perkins}}
U. S. Nuclear Regulatory Commission Update to the Inservice Testing (IST) Program Page 4 cc:
E. W. Merschoff J. W. Clifford J. M. Moorman K. E. Perkins}}

Latest revision as of 08:45, 29 October 2019

Informs That Plant Updating IST Program to ASME Boiler & Pressure Vessel Code,1989 Edition.Updated Program Will Take Effect on 980115.Second 10-yr IST Program Encl
ML17313A176
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 01/13/1998
From: James M. Levine
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17313A177 List:
References
RTR-NUREG-1482 102-04060-JML-S, 102-4060-JML-S, GL-89-04, GL-89-4, NUDOCS 9801210044
Download: ML17313A176 (10)


Text

CATEGORY j.

REGULA'1 Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)

ACCESSION NBR:9801210044 DOC.DATE: 98/01/13 NOTARIZED: NO DOCKET I FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-'50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFIL1ATION L'EVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECXPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Informs that plant updating IST program to ASME Boiler 8 ,c Pressure Vessel Code,1989 Ed@tv.on. Updated program wall take

~ ~

A effect on 980115.

4- t T DTSTRTBUTTON CODE: A047D CORTES RECEIVED:LTR I ENCL I SLEE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 E NOTES: STANDARDIZED PLANT 05000528G Standardized plant. 05000529 Standardized plant. 05000530p RECXPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA 1 1 PD4-2 PD 1 1 CLIFFORD,J 1 1 INTERNAL 1 1 AEOD/SPD/RAB 1 1 E 1 ' 1 NRR/DE/EMEB 1 1 NUD B~gta- CT 1 OGC/HDS2 1 0 RES/DET/EXB RES/DET/EMMEB 1 1 D EXTERNAL: LITCO ANDERSON 1 1 NOAC NRC PDR 1 1 E

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13

L cenmlbncnr.lematke,

&erg'alo James M. Levine TEL (602)3934300 Mail Station 7602 Verde Nuclear Senior Vice President FAX (602)3936077 P.O. Box 62034 Generating Station Nuclear Phoenix, AZ 65072-2034 102-04060 JML/SAB/JRP January 13, 1998 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS) 1,2, and 3 'nits Docket Nos. STN 50-528/529/530 Inservice Testing (IST) Second 10 Year Program In accordance with 10 CFR 50.55a (f)(4)(ii), Palo Verde. is updating the IST Program to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code, 1989 Edition. The updated program complies with the requirements of the latest edition and addenda of the ASME B&PV Code incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval. Subsections IWP and IWV of the Code refer to implementing the requirements of ASME / American National Standards Institute (ANSI) OM-6 and OM-10, respectively. Therefore, the update to the IST Program is based on the applicable requirements set forth in ASME/ANSI OM-1987, "Operation and Maintenance of Nuclear Power Plants,"

including the ASME/ANSI OMa-1988 Addenda. The updated program will take effect on January 15, 1998.

Augmented Testing Consistent with the philosophy and recommendations of Section 2.2 of NUREG - 1482, Guidelines for Inservice Testing at Nuclear Power Plants, Palo Verde has developed an augmented testing program for selected Non-IST components. These components have been integrated into the tables in Attachment (1) for convenience. Palo Verde chose to include " cold shutdown/refueling justifications" and "relief requests" for these non-code components to maintain consistency and clearly identify the basis for any "deviations" from the code.

980i2i0044, 980ii3 PDR ADQCK 05000528 P PDR j

, IIIIIIIIIIIIIIIIIIIIIIIII IIIIIIIIIII

U I

I I

U. S. Nuclear Regulatory Commission Update to the Inservice Testing (IST) Program Page 2 Summary of Relief Requests Table 1 contains a list of relief requests that are being submitted for NRC review and approval. Several of the relief requests document situations where complying with Code requirements is impractical, and are submitted in accordance with 10CFR 50.55a(f)(5) and (6). PVNGS will implement the relief associated with "impractical" tests while the NRC is reviewing the relief requests, as provided for in Section 2.5 of NUREG - 1482.

PVNGS will not implement "proposed alternative" tests until use of the alternative is authorized by the NRC per 10CFR 50.55a(a)(3).

Table 1 RR¹ Description Impractical/

Alternative PRR-03 Charging Pump Flow Rate Measurement Impractical PRR-07 Charging Pump Vibration Measurement Impractical PRR-08 Smooth-Running Pumps Proposed Alternative PRR-09 Evaluation as Corrective Action Proposed Alternative PRR-10 ANII Involvement in Pump Inservice Testing Proposed Alternative VRR-05 Downcomer Feedwater Check Valve Closed Exercising Impractical VRR-07 Containment Sump Check Valve Disassembly and Proposed Alternative Inspection Schedule VRR-08 PIV Closed Exercising Schedule Impractical VRR-09 Verification of Thermal Equilibrium During Safety/Relief Proposed Alternative Valve Testing VRR-10 Accumulator Volume for Safety/Relief Valve Testing Proposed Alternative VRR-11 ANII Involvement in Valve Inservice Testing Proposed Alternative VRR-12 MOV Exercising and Stroke Timing Proposed Alternative VRR-1 3 Check Valve Condition Monitoring Proposed Alternative The remaining relief requests document other types of Code deviations or approaches, which do not require specific NRC review or approval. These relief requests can be grouped into three general groups, as described below:

~ Deviations associated with au mented tests. Augmented tests are those tests that are not required by the ASME Code but are voluntarily included in the PVNGS IST Program for convenience. PVNGS policy is to perform augmented tests in accordance with the Code as far as practical. Deviations from Code requirements are documented as relief requests for consistency, but they do not require NRC approval because augmented tests are outside the scope of the IST Program.

U. S. Nuclear Regulatory Commission Update to the Inservice Testing (IST) Program Page 3

~ A roaches allowed b NUREG-1482. NUREG-1482 describes several approaches to testing that have been found acceptable by the NRC if their use is documented in the IST Program. PVNGS has documented the use of these approaches in relief requests for convenience. These relief requests do not require NRC review or approval because these approaches have already been found acceptable by the NRC.

~ Alternative testin a roved b Generic Letter 89-04. Generic Letter 89-04 granted approval to implement the alternative testing delineated in Positions 1,2,6,7,9, and 10 of the generic letter provided their use is documented in the IST Program. Use of these positions is documented in Relief Requests for convenience.

These relief requests do not require NRC review or approval because they follow the provisions of Generic Letter 89-04.

The description of the relief requests described above are contained in Attachment 1.

APS requests NRC review and approval of the relief requests listed in Table 1 above.

Im lementation Strate All tests performed after the implementation date will be conducted in accordance with the updated IST Program. The implementation of the second 10 year IST Program will require the performance of a number of new surveillance requirements. APS intends to treat these new requirements as being "met" at the time of implementation of the updated program. The first actual performance of the surveillance requirements will be scheduled within the specified frequency starting from the date of implementation. For surveillance requirements whose frequency of performance is being extended or shortened, the due date for the next performance of the surveillance will be changed to reflect the new required frequency upon implementation.

Should you have any questions regarding this matter, please contact Scott A. Bauer at (602) 393- 5978.

Sincerely, JML/SAB/JRP/rlh Enclosure

U. S. Nuclear Regulatory Commission Update to the Inservice Testing (IST) Program Page 4 cc:

E. W. Merschoff J. W. Clifford J. M. Moorman K. E. Perkins