ML20205J635

Summary of 990303 Meeting with Entergy Operations,Inc in Rockville,Maryland Re Status of Arkansas Nuclear One Backlog for Open Licensing Actions & Activities.List of Meeting Attendees & Licensee Handout Encl

ML20205J635
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/05/1999
From:	Nolan M NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9904120122
Download: ML20205J635 (33)

Text

E i LICENSEE: . Entergy Opsrations, Inc. April 5,1999 FACILITY: Arkansas Nuc!:ar One, Units 1 and 2

SUMMARY

OF MARCH 3,1999, MEETING WITH ENTERGY OPERATIONS,  !

INC., REGARDING ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 LICENSING {

ACTION AND ACTIVITY STATUS MEETING i On March 3,1999, representatives of the Nuclear Regulatory Commission (NRC) and Entergy Operations, Inc. (Entergy, licensee), met to discuss the status of the Arkansas Nuclear One

)

(ANO) backlog for open licensing actions and activities. The meeting was held at NRC Headquarters in Rockville, Maryland. A notice of this meeting was issued on February 17, 1999. Enclosure 1 is a list of attendees. Enclosure 2 is the licensee's handout used at the meeting.

l Entergy prnvided a preliminary summary of applications for licensing actions that they were preparing for future submittal. This information is useful to the NRC to allow better resource planr.ing efforts. . In addition, Entergy and the NRC discussed the quality of licensing submittals to share lessons learned in an effort to achieve a mutual goal of improved submittal quality result;ng in reduced NRC review times.

ORIGINAL SIGNED BY:

M. Christopher Nolan, Project Manager, Section 1 Project L'irectorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation  !

Docket Nos. 50-313 and 50-368 '/

Enclosures:

As stated (2) .

cc w/encls: See next page 7()

DISTRIBUTION:

HARD COPY E-MAIL Docket 1 S. Collins /R. Zimmerman (SJC1/RPZ) J. Tsao (JCT) i PUBLIC J. Zwolinski (JAZ)/S. Black N. Hilton (NDH)  ;

PD4-1 RF S. Richards (SAR) D. Lange (DJL) i C. Nolan R. Gramm (RAG) K. Brockman (KEB)

OGC L. Berry (LGB) ,

ACRS l DOCUMENT NAME: G:\ANOFINAL\MTS0303.WPD To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with j attachment / enclosure N = No copy j OFFICE PM/PD4-1 E LA/PD4-t . E SC/PD41 NAME ~- CNolan/vw LBerry h RGrammM DATE h/5 /99 ' 04/ 4 /99 04/ I /09 OFFICIAL RECORD COPY  !

l D a .g fh a cm j

l

, , pu:g g b UNITED STATES

= E NUCLEAR REGULATORY COMMISSION 1 WASHINGTON, D.C. 20S664001

• • • • • 1 April 5, 1999 LICENSEE: Entergy Operations, Inc.

FACILITY: Arkansas Nuclear One, Units 1 and 2

SUMMARY

OF MARCH 3,1999, MEETING WITH ENTERGY OPERATIONS, INC., REGARDING ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 LICENSING ACTION AND ACTIVITY STATUS MEETING On March 3,1999, representatives of the Nuclear Regulatory Commission (NRC) and Entergy Operations, Inc. (Entergy, licensee), met to discuss the status of the Arkansas Nuclear One (ANO) backlog for open licensing achons and activities. The meeting was held at NRC Headquarters in Rockville, Maryland. A notice of this meeting was issued on February 17, 1999. Enclosure 1 is a list of attendees. Enclosure 2 is the licensee's handout used at the meeting.

Ent?rgy provided a preliminary summary of applications for licensing actions that they were preparing for future submittal. This information is useful to the NRC to allow better resource )

plarning efforts. In addition, ?ntergy and the NRC discussed the quality of licensing submittals i to snare lessons learned in an e Mrt to achieve a mutual goal of improved submittal quality  ;

re'eulting in reduced NRC review times. ,

Q. hk& i M. Christopher Nolan, Project Manager, Section 1 Project Directorate IV & Decommissioning  ;

Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-313 and 50-368

Enclosures:

As stated (2) cc w/encts: See next page 4

1 .3 Entergy Operations, Inc. Arkansas Nuclear One, Units 1 & 2 cc:

Executive Vice President Vice President, Operations Support

& Chief Operating Off;cer Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-1995 Director, Division of Radiation Wise, Carter, Chied & Caraway Control and Emergency Management P. O. Box 651 Arkansas Department of Health Jackson, MS 39205 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Mr. C. Randy Hutchinson Vice President Operations, ANO Entergy Operations, Inc.

Winston & Strawn 1448 S. R. 333 1400 L Street, N.W. Russellville, AR 72801 Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525  ;

Rockville, MD 20852 j Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 -

London, AR 72847- '

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission j

~

611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 j County Judge of Pope County Pope County Courthouse Russellville, AR 72801 l

l 4

...m..._m.#-

p

, a March 3,1999 Meeting between Entergy Operations, Inc.

l and Nuclear Regulatory Commission ATTENDANCE LIST Name Affiliation 1

Chris Nolan NRC/NRR Nick Hilton NRC/NRR George Dick NRC/NRR Dale James Entergy Steve Bennett Entergy Clint Szabo Entergy l

l Enclosure 1

r .

hf 7

N j . .

1 2 ANO/NRC i

{

i

. 'l TACITIM i 1l j'

5 1

STATUS MEETING  :

4 l MARCH 3,1999 -

i

1. I

$/

., Enclosure 2 s --

NRC OPEN TAC NUMBERS l

\

01-Mar 99 TAC NO SUBJECT LEAD ACTION Ai'G-2 :noperable Channel "D" Excore Enforcement Decembon Scheide,R NRC t i

ANO 2 Exigeet TS Change ABowmg Startup withinoperah IPS Funchone Sanbo,C NRC M69426 GeneneLe874u MQ ';re fMecharuoa!andElecine o Mosher,N ANO Equipment (SQUG)

M69427 Oenenc Istler 8742 Sciemic Q=t#w=han ofMecharucal and Elecenc Mosher,N ANO Equipmmit(SQUG)

M83588 IPEEE for Extemal Events (OL 88-20 Supplement 4) Mosher,N ANO M83589 IPEEE for Extema! Events (OL 88-20 Supplement 4) Mosher N ANO M92435 ANO 2 LP irgschon Outage Time Extenman TSCR Cooper,R ANO Szabo,C M93427 RAI on Proesure Ieckmg and Thermal Binding of Oste Valves Bennett,8 NRC M93428 RAI on Pressure Iecking and Thermal Binding of Gate Valves Bennett,5 NRC M94643 Testing of Safety-Related legic Circuits Mosher,N NRC M94644 Testing of Safety-Related Iagic Circuite Mosher,N NRC M96775 Assurance ofEquipment Cr * ' ^j and Contamment Integrity (OL 9646) Mosher,N NRC M96776 Amourance ofEquipment Operabibly and Containment Integrity (OL 96 06) Mosher,N NRC M97013 OL 96 05 MOV Capability Penodie Verifiestion Bennett,S ANO M97014 OL 96 05 MOV Capability Periodic Venficanon Bennett,5 ANO M97528 ControlRoom Ventilation TSCR Sambo,C NRC i M97533 ControlRoom VentilationTSCR Szabo,C NRC M97750 Evaluate NonCode Repairs of SW Piping Bennett,S NRC M98543 Degradation of CRD Mechanical Nozzles and Other Vessel Closure Penetrations Mosher,N NRC M98544 Degradabon of CRD Mecharuc.1 Nozzles and Other Vessel Closure Li ;..;~n. Mosher,N ANO M99234 ANO 1 Relief Requett for Core flood /RPV Nozzle Exams Dosa,J NRC M99243 ANO 1 ISI Plan for Third 10 Year 1nterval Dosa,J ANO MA0523 ANO 1 Additionallnf rmation Concemmg BAW 2325 Mosher,N ANO ,

MA0524 RAI Regarding RPV Integrity at ANO 2 for OL 9241 Mosher,N NRC MA0893 Degradation of Steam Generator Inknnais Dosa,J NRC MA0894 Degradaban of Steam Generator Internels Dosa,J NRC MA1545 ANO 2 Append.x R Exemption Request . Service Water Intake Structurs Bennett,S NRC Mosher,N MA1546 ANO 1 Appendix R Clanficebon for MU Pump Room Lube Oil Pumpe Mosher,N NRC MA1547 ANO 1 ReliefRequest for RCS Wold Exame Dosa,J NRC MA1548 ANO 1 ReliefRequest for Reactor Vsessi Exame Dosa,J NRC MA1717 ANO 1 TSCR Regarding Dermition of Quadrant Power Tilt (QPT) Szabo,C NRC MA1718 ANO-2 Diese! Oonerator load Reyechon TSCR Szabo,C NRC MA1804 OL 9841 Y2K Readiness of Computer Systems et ANO Mosher,N ANO Page 1 of 2 j

. . TAC N3 SUBJECT LFAD ACTION j MAIB03 GL 98 01 Y2K Readirwes ofcomputer Systerrk c1 ANO 14uher,N ANO MA1951 Revww ofMethodology for SO Tube Integrity Dosa,; NRC MA2022 ANO 1 Second IntervalISIReliefRequets Dr aa,J NRC MA2023 ANO 1 Risk-BeeedISI Doen,J NRC MA2244 ANO 2 PPS USQ $0.90 &nnett,8 NRC MA2396 ANO 2 SG replacement Pro Application Meetings and Preparations Boyd,D ANO MA2397 ANO-2 Somoe Water to Spent Fue! PoolImak Mosher,N NRC MA2398 Various ANO 2 TS Bases Changes Cooper,R NRC MA2401 Open Equipment Hatch Dunng Core Aherstens Mostwr,N NRC MA2402 Open Equipment Ltch During Core Aheretions Mosher,N NRC MA2403 ANO 2 Design Tatures TSCR Cooper,R NRC szabo,C i

MA24M ANO-1 NaOH TSCR Szabo,C NRC MA2495 ANO 2 CEA Position Indication and Contaiment Penetration overcurrent Table Cooper,R NRC Relocation TSCR MA3588 Request to Use Code Cases 2142-1 and 2143-1 for SG Replacement Boyd,D NRC MA4367 QAMG Subrruttal Mosher,N NRO MA4368 Administrative Controls Section changes to support EDI cornmon QAPM esort Szabo,C ANO MA4381 QAMO Subnuttal Mosher N NRC j MA4382 Administrative Controls Section changes to support EOI common QAPM effort Szabo,C ANO MA4433 ANO-2 RSO Code Case 593 Boyd,D None t

I 1

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Page2 of 2 j

UpC: ming ANO Submittals .

l 03/01/1999  !

Tith CognhaatIndMdual Espected Date ANO 2 Revise Defmition of

• CORE ALTERATION" to the definition contained in Szabo,C 10/1/99 NUREO-1432, *CE ISTS" for use in 2R14.

i ANO 1ITS Subautta! Szabo,C 10/15S 9 ANO 1IST Third 10 YearInterval Dosa,J 10/969 ANO 1/2 TS Reactor Coolant Pump HywheelInspa tion TSCR Dosa,J 12/IS9 Genene Letter 37 02 Seismic Qualification ofMechanical and Electric Equipment Mosher,N 3/12 S 9 (SQUG)

IPEEE for External Events (GL 88-20 Supplement 4) Mosher,N 3/12/99 RAI on Pressure Locking and Thermal Emding of Gate Valves Bennett, S 3/15 S 9 Appendix RExempdon leHu DM Cooper,M 3/20S9 OL 9645 MOV Capbivj Periosic Verdinahna Bennett,S 3/20S9 ANO-1 Battery Requirements TSCR Szabo,C 3/25S 9 l ANO 2 TS Change Alkming RPS Inoperable Functus to Be Placed In Service For Schende,R 3/25S9 PPSIogie Matrix Testing ANO 1 IWL ReliefRequest Bennett, S 3/26S9 ANO-2 IWL ReliefRequest Bennett,S 3/2699 ANO Revise ESAS Iew RCS Pressure Setpoint Szabo,C 3/30S9 ANO 1/2 ContainmentTendon Inspection TSCR Szabo,C 4/199 ANO 2 Design Feeum TSCR Szabo,C 4/199 j l

ANO 2 RSO COLRTSCR Boyd,D 4/199 ANO 2 RSO ESFTSCR Boyd,D 4/199 l ANO 2 RSO Flow TSCR Boyd.D 4/199 ANO 2 RSO HU/CD TSCR Boyd,D 4/199 l ANO 2 RSO1nsp TSCR Boyd,D 4/169

/NO 2 RSO PT TSCR Boyd, D #199 ANO 2 RSO RPS TSCR Boyd,D 4/199 ANO 1 ARC for Out4de Diemeter Intergranu!nr Attack in the Upper Tube Sheet Does, J 4/1599 ANO-1 Tube End Cracking ARC TSCR Daes,J 4/15 S 9 Delete Requirements forPASS Boyd,D 400S9 ANO 1 ReroD and Multiple Retou TSCR Dosa,J 5/IIL99 ANO Revise Shutdown Cooling How Limits to Account fer Instmment Szabo,C CIS9 Uncertamties 50.12 Exemptions StiD in Efrect for License Renewal Per:od Mosher,N 6/1599 ANO-1 Appendix R Clarification for MU Pump R:om Lube Oil Pumps Mosher,N 6/15S9 ANO 1 Bases Change to Incorporate Statistical Core Doesn Mosher,N 6/15S9 ANO-2 I-800 Sleeves TSCR Dosa,J 6G0S9 Revise ANO 1 and ANO 2 specified curie content for Waste Ons Decay Tanks Szabo,C 7/199 ANO 1 leak Detection Instrumentation TSCR Bennett,S 8/1569 5 ANO-1 Purge Valve TSCR Mosher,N 9/1199 Page1of 1

) - . - . ---- 2

Arkans:s Nuclear O e TAC Report 01-Mar 99 TACNUMBER: UNTT: 2 ACTION: NRC COGNIZANTINDIVIDUAL: Scheide, R TTTLE: ANO.1 Inoperable channel "D" Excore Enforcement Discretion TASK: OUTAGE RELATED7: Yes WHICH OUTAGE: 2R13

SUMMARY

Channel "D" excore was inoperable prior to 2R13. Replacement detector failed. TS Table 3.3 1, Action 2, requires restoration to operable status prior to startup from next cold shutdown. Verbal enforcement discretion was requested on 2/23/99. The NRC verbally granted the enforcement discretion at 2002 CST on 2/23/99. This letter formally submits the request for enforcement  !

discretion. i STATUS: NRC toissue formalNOE9 ACTION NEEDED: NRC approval TAC NUMBER: UNTT: 2 ACTION: NRC COGNIZANTINDIVIDUAL: Szabo,C TITLE: ANO-2 Exigent TS Change Allowing Startup with Inoperable RPS Functions TASK: TSCR 2-99 03 OUTAGE RELATED?: No WHICH OUTAGE:

SUMMARY

Based on NOED dated 2/23/99 (2CAN029912), ANO-2 is to submit an exigent TS change within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to add a footnote to TS Table 3.3 1, Action 2, allowing the unit to startup from cold shutdown with inoperable RPS functions, due to Channel "D" excore being inoperable, until the ,

mid cycle outage (2P99).  !

&TATUS: 2/25/99 Submitted Exigent TS change to NRC ACTION NEEDED: NRC apprm1d i

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Page 1 of 22

TAC NUMBER: M69426 UNTT: 1 ACTl!N: ANO COGNIZANTINDIVIDUAL: Mosher,N TITLE: Generic letter 87 02 Seismic Quahfication of Mechanical and Electric Equipment (SQUG)

TAEK GL8742 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

In February,1987, the Nuclear Regulatory Commission (NRC) issued Generic Letter #87 02. The impact of the generic letter on ANO is that it will be nea amary to reevaluate the seismic adequacy of certain equipment ident2fied as " essential" per USI A-46 criteria. An owner's group, Seismic Quahfication Utility Group (SQUG), was formed during the initial stages of USI A-46 development to demonstrate that past carthquake experience data can be used to verify the maiemic adequacy of equipment at nuclear power plants. The efforts of the SQUG resulted in the NRC agreeing (in Generic I.etter #87 02) that the use of past earthquake experience data is an acceptable method of verifying the seismic adequacy of equiprnent in operating nuclear power plants and can be used as a basis for resolving USI A-46. With NRC codorsement and consent, I the SQUG has developed generic sesolution criteria and guidelines to be used in the implementation of the requirements of Generic letter #87 02 (Generic Implementing Piw: ,

GIP). The GIP was submitted in the Spring of 1988. In a letter dated March 11,1991, the NRC provided approximately 70 comments on Revision 2 of the GIF to SQUG.

l STATUS: In letter OCANO39108 (dated March 21,1991) Entergy Operations stated that due to the SER schedule slippage, the anticipated SQUG plant walkdowns would be deferred at least one refueling ,

outage; however, final schedules can only be determined after issuance of the SER. By NRC letter i dated May 22,1992 (OCNA059214), Supplement 1 to GL 87 02 was issued transmitting the SSER- j 2 on SQUG GIP-2, which requested licensees to provide a schedule for implementation of GIP-2

'within 120 days (due W=H 18,1992). Entergy Operations te on September 18,1992 (OCAN099201) and committed to implement GIP-2 during 1R11 with completion by May 1995. l The NRC responded on November 16,1992 (OCNA119210) with a Safety Evaluation and a request l for additional information. ANO responded to the Staffs request on January 28,1993 l (0CAN019307). The Staff had an additional request via telecon on the ANO 1 response spectra l and requested Entergy Operations to submit additional information within 60 days. Entergy Operations suomitted the requested information on March 26,1993 (ICANO39306). By NRC letter dated August 19,1993 (1CNA089303), the Staffissued the final safety evaluation for ANO-

1. 'Ihe Staff considered the ANO-1 floor response spectra as 'mekan centered" rather than

" conservative design." On May 31,1996 (OCAN059609), Entergy Operations submitted the summary report. By letters dated April 3,1998 (OCNA049808) and May 7,1998 (0CNA059606),

the NRC issued RAIs. ANO plans to respond to these RAls by mid-March 1999. The March response date is tied to theIPEEE RAL ACTION NEEDED: ANO to provide response to RAls Page 2 of 22

......_7_.

m

f TAC NUMBER: M69427 UNIT: 2 ACTION: ANO COGNIZANT INDIVIDUAL: Mosher, N TITLE: Generic Letter 87 02 Seismic Quahfication of Mechanical and Electric Equipment (SQUG)

TASK: GL 87 02 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

In February,1987, the Nuclear Regulatory Commission (NRC) issued Generic Letter #87 02. The impact of the generic letter on ANO is that it will be numary to reevaluate the seismic adequacy of certain equipment identi5ed as " essential

• per USI A 46 criteria. An owner's group, Seismic Quah5 cation Utility Group (SQUG), was formed dunng the initial stages of USI A 46 development to demonstrate that past earthquake expenence data can be used to venfy the seismic adequacy of equipment at nuclear power plants. Tbc efforts of the SQUG resulted in the NRC agreeing (in Generic 14tter #87-02) that the use of past carthquake experience data is an acceptable method cf venfying the seismic adequacy of equipment in operating nuclear power plants and can be used as a basis for resching USI A 46. With NRC endorsement and consent, the SQUG has developed generic resolution criteria and guidelines to be used in the impicmentation of the requirements of Generic Imer #87 02 (Generic Implementing Procedures, GIP). The GIP was submitted in the Spring of 1988. In a letter dated March 11,1991, the NRC provided approxunately 70 comments on Revision 2 of the GIP to SQUG.

STATUS: In letter OCANO39108 (dated March 21,1991), Entergy Operations stated that due to the SER schedule slippage, the anticipated SQUG plant walkdowns would be deferred at least one refueling outage; however, final schedules can only be determined aAer issuance of the SER. By NRC letter dated May 22,1992 (OCNA059214), Supplement I to GL 87 02 was issued transmitting the SSER-2 on SQUG GIP-2, which requested licensees to provide a schedule for implementation of GIP-2 ,

within 120 days (due September 18,1992). Entergy Operations responded on Pp**=har 18,1992 )

(OCAN099201), and committed to implement GIP-2 during 2R10 with completion by May 1995.

The Staff responded on November 16,1992 (0CNA119210) with a Safety Evaluation for ANO-2 and a request for additional information for ANO-1 (see TAC No. M69426). In May 31,1996 (OCAN059609), Entergy Operations submitted the summary report. By letters dated April 3,1998 l (0CNA049808) and May 7,1998 (OCNA059606), the NRC issued RAIs. ANO plans to respond to these RAIs by mid March 1998. The March response date is tied to the IPEEE RAL ACTION NEEDED: ANO to prmide response to RAls l l

l TAC NUMBER: M83588 UNIT: 1 ACTION: ANO COGNIZANT INDIVIDUAL: Mosher, N l

TITLE: IPEEE for External Events (GL 88-20 Supplement 4) l TASK: GL g8 20 OUTAGE RELATED7: No WlUCH OtfrAGE:

SUMMARY

Supplement 4 (IPEEE) to the generic letter was issued on June 28,1991. This supplement I required a response that describes the ANO proposed program within 180 days of rezipt. In letter l OCAN129101, dated December 19,1991, ANO committed to submit a schedule within 120 days following receipt of the SQUG GIP SSER. The GIP-2 SSER was received on May 22,1992.

! IrrATUS: Entergy Operations submitted letter OCAN099201, dated September 18,1992, committing to I perform our IPEEE during 1R11 with completion by May 1995. By NRC letter dated August 24, 1993 (OCNA089313), the Staff accepted ANO's schedule for completion of the IPEEE effort by May 1995. By letter dated April 4,1995 (0CAN049505), Entergy Operations committed to prmide a new submittal date with a response to GL 88-20 Supplement 5, which was later issued on September 8,1995. By letter dated October 16,1995 (OCAN109505), ANO responded to GL 88-20 Supplement 5 by indicating the desire to use the ' modified scope" rniew and committing to submit the IPEEE/USI A-46 mmmary reports by March 31,1996, which was subsequently changed to May 31,1996. On May 31,1996 (OCAN059609), Entergy Op: rations submitted the pnmmary report. By letter dated Apri13,1998 (OCNA049807), the NRC issued an RAI. ANO plans to respond to this RAI by mid-March 1999.

ACTION NEEDED: ANO to provide response to RAI PM. -

1

TAC NUMBER: M83589 ' UNrr: 2 ACrION: ANO COGNIZANTINDIVIDUAL: Mosher, N TITLE: IPEEE for External Events (GL 88-20 Supplement 4)

TASK: GL 88-20 OUTAGE RELATED?: No WIDCH OUTAGE:

SUMMARY

Supplement 4 (IPEEE) to the generic letter was issued on June 28,1991. This supplement .

required a response that describes the ANO proposed program within 180 days of receipt. In letter OCAN129101, dated December 19,1991, ANO committed to submit a achadale within 120 days following receipt of the SQUG GIP SSER. The GIP-2 SSER was received on May 22,1992.

STATUS: Entergy Operations submitteil letter 0CAN099201, dated E "-:718,1992 committing to perform our IPEEE during 2R10 with' completion by May 1995. By NRC letter dated August 24, 1993 (DCNA089313), the Staff accepted ANO's schedule for completion of the IPEEE effort by May 1995. Entergy Operations submitted a seismic scope reduction for ANO-2 on July 20,1994 (2CAN079401). This commitment change would have revised the ANO-2 meimmic IPEEE from a

" focused scope" to a " reduced scope" type evaluation. By letter dated November 17,1994 (2CAN119402), the Staff was not able to endorse this revised approach to perform a reduced scope

seismic evaluation and allowed the following options'. 1) Cantimie our current IPEEE programs and submit 9---f ^"IPEEE, or 2) Submit a request to a4ust the IPEEE schedule pendang formulation of an NRC position on possible reduced scope seismic evaluations. By letter dated ('

April 4,1995 (OCAN049505), Entergy Operations committed to provide a new submittal date with a response to GL 88-20 Supplement 5, which was later issued on Eg^ =* : 8,1995. By letter dated October 16,1995 (OCAN109505), ANO responded to GL 88-20 S ;- 5==t 5 by indicering the desire to use the "madinad scope" review, and committing to submit the IPEEE/USI A-46 summary reposts by March 31,1996, which was subsequently changed to May 31,1996. On May 31,1996 (OCAN059609), Entergy Operations submitted the summary report. By letter dated April 3,1998 (OCNAC49307), the NRC issued an RAI. ANO plans to respond to this RAI by mid-March j 1999, i ACTION NEEDED: ANO to provide response'to RAI TACNUMBER: M92435 UNTT: 2 ACTION: ANO COGNIZANTINDIVIDUAL: Cooper,R COGNIZANT INDIVIDUAL: Szabo, C TITLE: ANO-2 If Iqjection Outage Time Extension TSCR TASK: TSCR 2-95 06 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

Extend the allowed outage time for an inoperable LPSI train to 7 days. This submittal is part of a CE Owner's Group initiative.

STATUS: On May 19,1995 (2CAN059502), Entergy Operations impsied to extend the allowed outage time for an inoperable LPSI train to 7 days. A meeting with the Staff was conducted on-site on January 25,1996 to dit:uss responses to NRC questions. ANO provided formal responses to these questions on February 27,1996 (2CAN029609), and responses to additional informal questions on k,=^- "- E 30,1996 (2CAN099604). A copy of the Operations Liaison Desk Guide was informally y,44dsd to the NRC on October 2~,,1996. The Staff has concluded that a configuration risk management program (CRMP) incorporated into the hoense is necessary to add PRA-based AOT extensions to the TS. A CRMP has been developed by the CEOG and reviewed and accepted ly the NRC. Entergy Operations has verbally informed the NRC ofits withdrawal as lead plant for the CEOG on the PRA based technical specification changes. Based on discussions with the NRC PMs, ANO desires to pursue a modified approach to resolution of LPSI AOT extension by applying a risk matrix approach versus a full CRMP.

2/5/99 Based on available resources ANO has decided to withdraw.

2/16/99 ANO submitted withdrawal letter 2CAN029906. j ACTION NEEDED: NRC Closure

. Page4 of 22

V TACNUMBER: M93427 UNIT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Rennekt, g TITLE: RAI on Pressure Iacidag and Thermal Binding d Gote Valves l

TASK: GL 95 07 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

By lener dated October 16,1995 (0CAN109509), ANO responded to the generic letter. A diig evaluation and operability basis of safety related power operated gate valves potentially susceptible to pressure locking and thermal binding had been completed. An additional response was planned to be submitted on February 13,1996, h;1dag ihrther :=g'"-1 analyses, ,

corrective actions to ensure identi5ed susceptible valves are capable ofM .Jiig their intended safety neia=_. and a completion schedule for any planned equipment or procedural

=adine=' ions. On Fetmary 13,1996, Entergy Operations submitted the 180 day response which documents the results of evaluations performed for pressure locking and thermal binding per GL 95 07 for 214 Unit I and Unit 2 safety-related power operated gate valves (i.e., all safety-related power operated gate valves at ANO). A total of 56 valves for both ANO units combined were identified as potentially susceptible to binding and locidag. A total of 9 valves for both ANO units combined 'were determined to be susceptible to pressure locidag STATUS: A request for additional information was received from the NRC. ANO responded to the four questions in a letter to the NRC dated July 15,1996 (0CAN079601). Modificationswere made to CV 2803 and CV 2806 (EFW P7A/B SW Suction Taalatian Valves) during refbening outage IR13 l

in accordance with commitments made in our letter dated February 13,1996 (OCAN029605).  ;

Modifications have been completed for the ANO-1 valves. GGNS has subsequently recorved an informal RAI bom the NRC regarding their prediction methodology for pressure locidag and 4 thermal bindmg of valves. ANO's and other EOI site's prediction ,,,. s is based on the GONS l methodology. A draA RAI was sent to ANO in January 1999 containing eight follow-up quantiana These RAls were discussed with the NRC on Feb 23,1999 and either addressed or consohdated to a few RAls. NRC will provule formal RAIs with a 30 day response. EOI intends to respond to the RAIin April 1999.

ACTION NEEDED: NRC toissue RAI i

I 4

0 8 e Pas 5 of 22

TACNUMBER: M93423 UNrr: 2 ACTION: NRC COGNIZANTDtDIVIDUAL: haneet $

TrrLE: RAI on Pressure Imeldag ar.d Thermal Bin &ng of Gate Valves TASK: GL 95 07 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

By letter dated October 16,1995 (0CAN109509), ANO responded to the generic letter. A screening evaluation and operability basis of safety related power operated gate valves pan,ne..ny susceptible to pressure locidag and thermal binding had been completed. An additional response was planned to be submitted on February 13,1996, M_== fbrther ocmpleted analyses, wi 4;vs actions to ensure identinad susceptible valves are capable of performing their intended safety fhnetion, and a completion schedule for any planned equipment or procedural modifications. On February 13,1996, Entergy Operations submitted the 180 day response which deinwn's the results of evaluations perfonned for pressure locking and thermal binding per GL 95 07 for 214 Unit 1 and Unit 2 safety-related power operated gate valves (i.e., all safety-related power operated gate valves at ANO). A total of 56 valves for both ANO units combined were identified as aa*='i=Hy susceptible to bin &ng and locking A total of 9 valves for both ANO units combined were determined to be susceptible to pressure locking.

STATUS: Mo&fications were planned for 4 valves during the 2R12 refueling outage (May 9 - June 9,1997).-

One of the 9 susceptible valves was determinad acceptable based on procedural controls. In addition to any pressure locking ==aMh".11 valves have procedural changes in place to mitigate the potential for thermal bin &ng or pressure locidng A request for additional information was received from the NRC. ANO responded to the four questions in a letter to the l NRC dated July 15,1996 (OCAN079601). Three of the four valves were =adinad as planned during the 2R12 refbeling outage The SW to FEW pump isolation valves 2CV 0711-2 and 2CV-0716-1 and the red train containment spray header isolation valve 2CV-5612 1 were madinad as scheduled during 2R12; however, modification of the green train containment spray header isolation valve 2CV-5613-2 has been postponed until t but modified during 2R13. This change in commitment was discussed with the ANO NRR project manager on May 29,1997, and followed up with a docketed submittal on June 4,1997 (2CAN069706). GGNS has racerved an informal RAI from the NRC regar&ng their prediction methodology for pressure locking and thermal binding of valves. ANO's and other EOI site's prediction approach is based on the GGNS methodology. A draA RAI was sent to ANO in January 1999 containing twenty follow-up questions. These RAIs j were discussed with the NRC on Feb 23,1999 and either addressed or consolidated to a few RAIs.

NRC will provide formal RAls with a 30 day response. EOI intends to respond to the RAI in April 1999.

. ACTION NEEDED: NRC to provide RAI TACNUMBER: M94643 UNIT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Mosher, N TITLE: Testing of Safety-Related Logic Circuits TASK: GL 96 01 O TAGERELATED7: No WHICH OUTAGE:

SUMMARY

FTATUS: By letter dated April 19,1996 (0CAN049603), ANO provided the 60 day response to Generic letter 96 01, " Testing of safety-Related I.cgic Cirmits". In response to GL 96 01, a reyww of the RPS and ESAS was performed in order to identify la=daaaa'a logic testing. The review included RPS, ESAS, and EFIC. ANO provided closure submittal June 10,1998 (ICAN069805).

ACTION NEEDED: NRC closure Page 6 of 22

== , . = = . - - - . .

TACNUMBER: M94644 UNfT: 2 ACTI::M: NRC COGNIZANTINDIVIDUAL: Mosher, N ,

TITLE: Testing of Safety-Reinted Iagic Circuits I TASK: GL 96 01 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

rTATUS: By letter dated April 19,1996 (OCAN049603), ANO provided the 60 day response to Generic letter 96 01. In response to GL 96 01, a review of the RPS and ESAS will be performed. 'Ihe review was completed by April 11,1997, for ANO 2. 'Ihe review included RPS. This close out was danimentad in co.. si.dence dated July 9,1997 (2CAN079713).

ACTION NEEDED: NRC closure TACNUMBER: M96775 UNIT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Mosher, N T'TLE: Assurance ofEquipment Operability and cantainment Integrity (GL 96 06)

TASK: GL 9606 OUTAGE RELATED7: No WIDCH OUTAGE:

SUMMARY

STATUS: By letter dated January 28,1997 (0CAN0197d2), ANO provided the 120 day response to Generic letter 96 06. The letter stated that the unit was determined to be operable with regard to water hammer, two-phase flow, and thermal aspM.Gon. A commitment was made to conduct further analysis and resulting modifications by refueling outage IR14 for the water hammer issue.

Regardag the tmhase flow issue, ANO 1 does not have significant two phase flow problems.

Two-phase flow was evaluated by a caladadaa performed prior to the generic letter. Regarding overpeessuruation ofisolated piping sections, the evaluation identined 21 containment building penetrations susceptible to thermal m  : ::= Immediate operability was determined to be assured ANO pursued analytical resolutions of this issue with the industry but was un====Ad at gaining NRC = rp== Final resolution of GL 96 06 was provided to the NRC on July 31,1997 (0CAN079710). In this letter ANO committed to moddications during the IR14 outage. On November 13,1997 (OCNA119705), the NRC issued Supplement I to GL 9606. ANO responded to the supplement on December 17,1997 (OCAN129703), and infonned the NRC that a schedule extension was necessary in order to pursue resolution which would not potentially decrease plant safety. ANO plans to provide another submittal of our exact plans once an acceptable resolution -

process is de5ned. By letter dated April 14,1998 (OCNA049812), the NRC issued an RAI concerning the July 31,1997 submittal. ANO responded to the RAI on January 25,1999 (OCAN019903).

ACTION NEEDED: NRC review and closure .

Page7of 22

,* wm e -=eww d* ' * *

• 4 *

• TACNUMBER: M96776 UNrrs 2 ACHON: NRC COGNIZAffrINDIVIDUAL: Mosher,N TrrLE: Assurance ofEquipment Operability and Containment Integrity (GL 9646)

TASK: GL 96 06 OUTAGE RELATEDt: No WIDCH OUTAGE'.

SUMMARY

STATUS: By letter dated January 28,1997 (0CAN019702), ANO provided the 120 day response to Generic letter 96 06. The letter stated that the unit was deternuned to be operable with regard to water hammer, two phase flow, and thermal overpressurization. A conunitment was made to conduct further analysis and resulting modifications by,refbcling outage 2R13 for the water hammer issue.

Regarding the two phase flow issur , ANO 1 does not have significant two-phase flow problems.

Two-phase flow was evaluated by a calculation performed prior to the generic letter. Regarshng m ,c.: ' =6a ofisolated piping sections, the evaluation identi5ed 11 containwne building penetrations susceptible to thermal overpressurization. tmmediate operability was determined to be assured. ANO pursued analytical resolutions of this issue with the industry but was unmanamand at gaining NRC acceptance Final resolution of GL 96 06 was provided to the.NRC on July 31,1997 (OCAN079710). In this letter ANO committed to nwhAcatiana during the 2R13 outage. On November 13,1997 (0CNA119705), the NRC issued S--g-f 1 to GL 96 06. ANO responded to the supplement on Da==her 17,1997 (OCAN129703), and informed the NRC that a schedule extension was necessary in order to pursue resolution which would not potentially decrease plant ~

safety. ANO plans to provide another submittal of our exact plans once an = =;-A *: resolution process is dennad By letter dated April 14,1998 (OCNA049812), the NRC issued an RP concerning the July 31,1997 submittal. ANO responded to the RAI on January 25,1999 ,

(OCAN019903).. j ACTION NEEDED: NRC review and closure l I

1 TACNUMBER: M97013 UNrT: 1 ACnON: ANO COGNIZANTINDIVIDUAL: Bennett, S  !

'hTrLE: GL 96 05 MOV Capability Periodic Ven5 cation TASK: OUTAGE RELATED7: No WHICH OITTAGE:

SUMMARY

Entergy Operations developed a periodic veri 5 cation program that wiL ensure long term design basis capability of the safety-related MOVs withirra scope of GL 9645. This program is i documented in company is 1-s DC-110, " Periodic Verification," which became effective January 27,1997.

4 STATUS: As committed in letter dated March 17,1997 (OCAN039705), the program will be implementad at ANO within 120 days of the completion of refbeting outage 2R12 which was completed on June 9, 1997. The pJam implementation is complete. On October 30,1997, the NRC issued a Safety  ;

Ersluation u. &c Joint Owners' Group Topical Report NEDC-32719 (Revision 2). The SE stated  ;

that the Staff considers Revision 2 of the Joint Owners' Group (JOG) Frogram on MOV Periodic 1 Verification an acceptable industry-wide response to Generic I. meter (GL) 96-05. He JOG agreed that a5cr the issuance of the SE, participating utilities would notify the NRC of their plans to implement the JOG program described in Revision 2 of the topical report and any deviations fkosa the JOG program would bejustified. ANO continues participation in the JOG MOV-Periodic Veri 5 cation Program and plans to implement the program clernents described in Revision 2 ef the topical report. De ANO MOV program has been mod: Sed to meet Rev 2 of the JOG. EOIinten provided a submittal on meeting Revision 2 of the JOG on Janusry 11,1999. Su%4, a draft RAI was provided to ANO regarding closure of final questions on MOV periodic verifkation.

ANO will call the NRC to discuss in early March 1999. ,

ACTION NEEDED: ANO to discuss response to dra5 RAI

^

Page 8 ef 22 m _.u r- - _. - ~- - -

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TAC NUMBER: M97014 UNrt: 2 ACTION: ANO COGNIZANTINDIVIDUAL: Bennett, S TrrLE: GL 96-05 MOV Capability Periodic Verification TASK: OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

Entergy Operations developed a periodic verification program that will ensure long term design basis capability of the safety-related MOVs within a scope of GL 96-05. This program is documented in company procedure DC-110. " Periodic Verification," which he== effective January 27,1997.

STATUS: As committed in letter dated March 17,1997 (OCANO39705), the program will be implemented at i

ANO within 120 days of the completion of refueling outage 2R12 which was completed on June 9, 1997. The program implementation is complete. On October 30,1997, the NRC issued a Safety Evaluation on the Joint Oners' Group Topical Report NEDC 32719 (Resision 2). The SE stated l that the Staff considers Revision 2 of the Joint Oners' Group (JOG) Program on MOV Periodic l Verification an acceptable industry-wide response to Generic letter (GL) 96-05. The JOG apeed that after the issuance of the SE, participating utilities would notify the NRC of their plans to imple:nent the JOG program described in Revision 2 of the topical report and any deviations from the JOG program would bejustified. ANO continues participation in the JOG MOV-Periodic Verification Program and plans to implement the program elements described in Revision 2 of the topical report. The ANO MOV program has been mod fied to meet Rev 2 of the JOG. EOI provided a submittal on meeting Revision 2 of the JOG on January 11,1999. Subsequently, a draft RAI was prmided to ANO regarding closure of final questions on MOV periodic verification.

ANO will call the NRC to discuss in early March 1999.

ACTION NEEDED: ANO to discuss response to RAI TACNUMBER: M97528 UNIT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Szabo, C TITLE: ControlRoom Ventilation TSCR TASK: TSCR0-94 04 OUTAGE RELATED7: No WHICH OITTAGE:

SUMMARY

Extend the allowable outage time for the control room emergency chillers from 7 days to 30 days and to prmide consistency between the ANO 1 and ANO-2 surveillance tasting requirements.

STATUS: On June 8,1995 (OCAN049501), Entergy Operations submitted a request to extend the allossble outage time for the control room emergency chillers from 7 days to 30 days and to provide l consistency between the ANO-1 and ANO-2 surveillance testing requirements. On De- 12, 1995, preliminary RAIs on filter testing requirements were faxed to ANO. On May 3,1996, Entergy Operations provided verbal comments on proposed filter testing requirements. ANO and the NRC agreed to use ASTM-D3803 testing methodologies for control room ventilation. ANO submitted a prcposed change consistent with this standard on December 19,1996 (OCAN129603).

A new control room air intake duct monitor was installed as a result of discussions on TS A=ndment 190. ANO committed to revise the submittal to incorporate the new monitor by August 1,1998. Revised submittal was transmitted to the NRC on August 6,1998.

It was identified that a reference table provided in the Dec.19,1996 submittal ass in error. ANO to prmide supplement correcting table error and prmide additional information on containment.

I ACTION NEEDED: ANO to provide additional informatian Page 9 of 22

l TACMUMBER: M97533 UNFr: 2 ACTION: NRC COGNIZANT INDIVIDUAL: Stats, C TrTLE: ControlRoom Ventilation TSCR TASK: TSCR 0-94 04 OUTAGE REIATED7: No WHICH OUTAGE: l

SUMMARY

Extend the allowable outage time for the control room emergency chillers Dom 7 days to 30 days l and to pnmde consistency between the'ANO-1 and ANO-2 surveillance testing ,%.J.- i l

STATUS: On June 8,1995 (0CAN049501), Entergy Operations suLmitted a request to extend the allowable outage time for the cont.ml room emergency chillers Aom 7 days to 30 days and to provide consistency between the ANO 1 and ANO-2 survallance testing reonire=* ate On December 12, 1995, pd:=:..sy RAIs on filter testing requireraents were faxed to ANO. On May 3,1996, Entergy Operations provided verbal comments on proposed filter testing regarements ANO and the NRC agreed to use ASDf D3803 testing methodologies for control room ventilation. ANO submitted a proposed change maatssent with this standard on December 19,1996 (OCAN129603).

A new control room air intake duct monitor was ia=#attad as a result of d>=iania== on TS Amendnut 190. ANO committed to revise the submittal to incorporate the new monitor by August 1,1998. Revised submittal was trnasmitted to the NRC on 8/6/98. 1 l

It was identified that a reference table provided in the Dec.19,1996 submittal was in error. ANO I to provide .oryterent correcting table error and provide additional information on ==tainsaane ACTION NEEDED: ANO to pnmde additionalinformation TACNUMBER: M97750 UNFri . C ACTION: !?RC COGNIZANTINDIVIDUAL: hanert, S TrrLZ: Evaluate Non-Code Repairs cf SW Piping  ;

1 TASK: OUTAGE RELATED7: No WHICM OtrTAGE: )

SUMMARY

STATUS: ANO letter dated November 4,1996 (OCAN119602), requested temporary relief to allow a non-code repair of the service water piping as required by Generic Letter 90 0$, " Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1,2, and 3 Pipe #* A three drop i

per minute leak from the ANO-214op 1 semce water supply line to the "B" emerJency feedwater pump was observed The piping was replaced during refueling outage 2R12 (May 1997). J AMitionally, the letter included a request for future generic reliefin order to reduce the administrstive burden on both ANO and the NRC. De letter provided speci6c criteria that must  !

be met befort generic relief would be invoked. Relief for temporary repair was granted on May 28, 1998(OCAN059822). A conference call with the NRC is necessary to obtain further informatnon on what is required for generic relief to ASME. De listing of SW piping segments that reliefis being requested was sent to the NRC on January 21,1999 (OCAN019902).

AcrION NEEDED: NRC to provide relief approval l

L Page10 of 22

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l TACNUMBER: M98543 UNrra 1 ACTION: NRC COGNIZANTINDIYtDUAL: Mosher,N TrrLE: Degradation of CRD Machaaient Nozzles and Other Vessel Closure Penetratices TASK: GL 9741 OUTAGE REIATED7: No WIGCH OUI AGE:

SUMMARY

! STATUS: By letter dated July 29,1997 (0CAN079703), Entergy Operations suhitted our response to Generic I.4tter 9741 for ANO. ANO 1 is partid,*In in a BWOG initiative to perform fbture inspections at Oconee and Crystal River and evaluate !!4 rusidts. This submittal concluded that there was no near-term safety concera; however, inspections were committed to be performed and the results evaluated. NEI provided a common industry response to address the RAls in December 1998. A formal letter requesting aNO response to the nozzle cracidag was received on12/8/98.

ANO has committed to pro ride our response to the NRC RAI by March 1,1999. Response was

- submitted on February 24,1999 (0CAN029908).

~

ACTION NEEDEDi NRC review and closure TACNUMBER: M98544 UNIT: 2 ACTION: ANO COGNIZANTINDIVIDUAL: Mosher N TITLE: Degradation of CRD Mechanical Nozzles and Other Vessel Closure Penetrabons TASK: GL 9741 OUTAGE RELATED7: No MUCH OUTAGE:

SUMMARY

STATUS: By letter dated July 29,1997 (OCAN079703), Entergy Operations submitted'our rwponse to Generic Imter 9741 for AF3. ANO 2 is participatmg in a CEOG initiative to perform fheure inspections at Millstone and SONGS and evaluate the results. 'Ihis submittal concluded that there this was not a safety sigm6 cant issue; however, inspections were committed to be performed and the results evaluated. NEI provided a common industry response to address the RAIs in Darendwr 1998. A formal letter requesting ANO response to the nozzle cracking was received on12/8/98.

ANO has committed to provide our response to the NRC RAI by March 1,1999. Response was submitted on February 24,1999 (0CAN029908).

ACTION NEEDED: NRC review and closure )

I TAC NUMBER: M99234 UNrra 1 ACT10N: NRC COGNIZANTINDIVIDUAL: Dosa,J  !

TITLE: ANO-1 ReherRequest for Core Flood /RPV Nozzle Exams )

TASK: OUTAGE RELATED?: Yes WHICH OUTAGE: IR15

SUMMARY

*Ihe relief request would utilize UT for the inside diameter of the for flood nozzle welds as described by Revision 1 of BAW 2228P.

STATUS: Relief request 96 003 was submitted to the NRC on August 26,1996 (ICAN089605). '!)e relief I request would utilize UT for the inside diarreter elthe four flood nozzle and six RPV welds as  :

described by Revision 1 of BAW-2228P. At the request of the Staff, the relief request was awlifid !

and resubmitted on June 16,1997 (ICAN069703). Needed by 1R15 (Sept 1999). NRC approval l providedin February 1999.

ACTION NEEDED: NRC Closure

\

Page 11 of 22

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TACNUMOFR: M99243 UNrT: 1 ACTION: ANO COGNIZANTINDIVIDUAL: Dosa,J TrTLE: ANO-1 ISI Plan for Third 10 Year Interval 1 TASK:' OUTAGERELATEDh No WADCH OUTAGE:

SUMMARY

STATUS: On June 25,1997, the inservice inspection plan for the third 10 year interval at ANO d was submitted to the Staff (1CAN069705). Three requests for alternatives requiring Staff review and approval were included in this submittal. ANO received an RAI on D- =har 2,1997 (ICNA129701) with a due date of Decembw 31,1997. The requested drawings were provided to l the reviewer in May 1998. The remale f the o ANO submittal was provided on December 9, l 1998.

ACTION NEEDED: NRC approval l TACNUMBER: MA0523 UNIT: 1 ACTION: ANO COGNIZANTINDIVIDUAL: Mosher,N TrrLE: ANO 1 AdditionalInformation G=- ' ;BAW-2325 TASK: GL 9241 OUTAGERELATEDh No WHICH OUTAGE:

SUMMARY

STATUS: During the review to support a previous GL 9241 RAI, B&W discovered an error in the ANO 1 l plant specific data. It did not affect the limiting r cid; however, ANO plans to submit a correction in March 1999.

ACTION NEEDED: ANO submittal TACNUMBER: MA0524 UNrr 2 ACTION: NRC COGNIZANTINDIVIDUAL: Mosher, N l TrrLE: RAI Regardmg RPV Integrity at ANO-2 for GL 9241 TASK: GL 9241 OtrrAGERELATEDh No WHICH OUTAGE:

j

SUMMARY

STATUS: By letter dated June 18,1997, Enteg Operations, Inc., submitted information that included the ,

compilation of data for reactor vessel materials by the Combustion Engineering Owners Group and  !

fluence evaluations for ANO-2. By letter dated August 13,1998 (2CNA089803), the NRC issued  ;

an RAI concerning the ANO response to GL 9241. Revision 1 Supplement 1. The response was requested within 75 days wLich will be by November 4,1998. By letter dated November 2,1998 (2CAN119803), Entergy Operations provided the requested information.

l ACTION NEEDED: NRC closute 4

. Page 12 of 22 c -

1 TAC NUMBER: MA0893 UNIT: 1 ACTION: NRC COGNIZANTINDMDUAL: Dosa,J TITLE: Degradation of Steam Generator Internals TASK: GL 97 06 OUTACE RELATED7: No MDCH OUTAGE:

1

SUMMARY

On December 30,1997, the NRC

• Cissued Generic letter 97 06 e alent addressees to findings of steam generator internals dams a foreign and U.S. facilities aral to request information concerning programs for inspection of steam gu ..; internals. Specifically, addressees were

! requested to describe programs in place to detect degradation of steam generator internals, discuss plans and schedules for developing such a program if one does not exist, orjustify why no programis needent FrATUS: On March 30,1998 (OCANO39808), ANO submitted our response to the generic letter ANO participated in the development of generic guidance documents to address degradation of steam generator internals with NEI Steam Generator Internals Task Force and the BWOG. Evaluation of inspection data from the ANO 1 steam generators and those of similar design laamt= no short term concerns with degradation of steam generator internals. The BWOG is currently developing a process to determine if a formal inspection program is -ry for steam generator in:ernals of once-through steam generators, including those at ANO 1.

ACTION NEEDED: NRC closure TAC NUMBER: MA0894 UNIT: 2 ACTION: NRC COGNIZANT INDIVIDUAL: Dosa, J TrrLE: Degradation of Steam Generator Internals TASK: GL. 97 06 OUTAGE RELATED?: No WIUCH OUTAGE:

SUMMARY

On December 30,1997, the NRC Staffimod Generic letter 97 06 to alert addressees to findings of steam generator internals damage at foreign and U.S. facilities and to request information concerning programs for inspection of steam generator internals. 5, ciar.ny, addressees were requested to describe programs in place to detect degradation of steam generator internals, discuss plans and schedules for developing such a program if one does not exist, orjustify why no programis needed.

ETATUS: On March 30,1998 (OCANO39808), ANO submitted our response to the generic letter ANO participated in the development of generic guidance documents to address degradation of steam generator internals with NEl Steam Generator Internals Task Force and CEOG Evaluation of inspection data from the ANO 2 steam generators and those of similar design indicates no short term concerns with degradation of steam generator internals. 'Ihe ANO-2 steam generators have undergone extensive secondary side inspections which are considered suf5cient until the steam j generatc.a are replaced in the fall of 2000. l ACTION NEEDED: NRC closure .

Page 13 of 22

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TAC NUMBER: MA1545 UNIT: 2 ACTION: NRC COGNIZANT DfDIVIDUAL: Re-n, S

. COGNIZANTINDIVIDUAL: Mosher,N l TITLE: ANO 2 Appendix R Exemption Request - Service Water Intake Structure TASK: OUTAGERELATEDh No WlUCH OUT ^ GE:

l

SUMMARY

STATUS: .By letter dated October 81997 (2CAN109703), ANO submitted an Appendix R exemption request for' lack of an automatic suppression system and lack of an automatic detection system for the area below 354' of the ANO-2 intake structure. This was due to Are wrap being installed on incorrect conduit. During discussions with the NRC Reviewer 'tional clari5 cation was requested on outage control activities. ANO provided the addit! . Arifying information on February 25, 1999. .

ACTION NEEDED: NR'C approval TACNUMBER: MA1546 UNIT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Mosher,N TrTLE: ANO 1 Appendix R Clari5 cation for MU Pump Room Lube Oil Pumps TASK: OUTAGERELATEDh No WHICH OtTTAGE:

SUMMARY

STATUS: . By letter dated October 22,1997 (ICAN109704), ANO submitted a clarification regarding one-hour Src barriers and an automatic Bre suppression system for the ANO 1 makeup pump rooms.

Control and power cables for the auxiliary lube oil pumps are routed near the floor without Are wrap. Due to maintenance activities possibly damaging the Sre wrap, ANO wishes to leave them unwrapped.

ACTION NEEDED: NRC approval TAC *JMBER: MA1547 UNIT: 1' ACTION: NRC COGNIZANT INDIVIDUAL: Dona,J TITLE: ANO-1 Relief Request for RCS Weld Exams TASK: OUTAGE RELATEDh No WHICH OUTAGE:

SUMMARY

Code Case N 460 requires that when the entire examinnhon volume or area cannot be evaminal due to interference by another component or part geometry, a reduction in examination coverage on any class I or class 2 weld may be accepted pivvMsd the reduction in coverage for that weld is less than 10%. During refueling outage IR11, which ended in October of 1993, the two pressure-retaining welds listed above received an examination that had a reduction in coverage for the weld greater than the 10% allowed by Code Case N-460 i@.i.ats. The lack of completeness of the examination is a result oflimited accessiillity due to geometry and interference by another i

component.

STATUS: By letter dated December 3,1997 (ICAN129703), ANO submitted a relief requestl ===== we were unable to exanune 100% of the weld volumes of two reactor coolant system welds during the last inservice iaW aal A conference call was held to provide clan 6 cation on 2/18/99.

ACTION NEEDED: NRC approval Page 14 of 22

. ... . . . . . . . - - . . . . ~ .

TACNUMBER: MA1548 UNIT: 1 ACTI!N: NRC COGNIZANTINDIVIDUAL: Dosa,J l

TTTLE: ANO 1 Relief Request for Reactor Vessel Exams TAEK: OUTAGE RELATED7: No WIUCH OUTAGE:

SUMMARY

During .d4 outage IR12, which ended in March 1995, four of the pressure-retaining welds in the ANO-1 reactor vessel received an --tauton that was less than the required 90%

examination volume. %c incomplete evaminatian resulted from limited accessibility due to the geometry of the reactorvessel STATUS: By letter dated October 23,1997 (ICAN109705), ANO submitted a relief request for the augmented reactor vessel shell welds because we were unable to examine greater than 90% of four reactor vessel welds due to reactor vessel interference.

ACTION NEEDED: NRC approval TACNUMBER: MA1717 UNTT 1 ACTION: NRC COGNIZAPrT INDIVIDUAL: Szabo, C TITLL ANO-1 TSCR Regarding Definition of Quadrant Power Tilt (QPT)

TASK: TSCR 1-98 02 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

Delete the portion of the QIrr definition which implies that the use of excore power range detectors is the preferred method for monitoring reactor core QI'T. This would align the ANO.1 QIrr definition with that contained in the ITS, NUREG 1430, Revision 1. Implementation of the revised definition will establish the incore detectors as the preferred methodology for monitoring QPT.

STATUS: By letter dated April 30,1998 (ICAN049802), Entergy Operations proposed a revision to the ANO-1 TS.

ACTION NEEDED: NRC to issue TS amend = eat TAC NUMBER: MA1718 UNIT: 2 ACTION: NRC COGNITANTINDIVIDUAL: Szabo, C l

TTTLE: ANO-2 Diesel Generator IAad Rejecten TSCR TASK: TSCR2 9130 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

Revise the value speci6ed for the single largest load associated with the ANO-2 diesel generators.

De value has been relocated to the bases consistent with NUREG-1432 praentation of this information.

STATUS: By letter dated April 30,1998 (2CAN049802), Entergy Operations proposed revision of the ANO-2 TS.

ACTION NEEDED: NRC toissue TS amendment TAC NUMBER: MA1804 UNIT: 1 ACTION: ANO .COGNIZANTINDIVIDUAL: Mosher,N TITLE: GL 98 01 Y2K Readiness of Computer Systems at ANO TASK: GL 98 01 OtTTAGE RELATED7: No WIDCH OITTAGE:

SUMMARY

STATUS: By letter dated Augua 10,1998, the 90 day response to GL 98 01 was pavvided to the NRC. A response confirming our Y2K rnadinas will be subr. tined by July 1,1999.

ACTION NEEDED: ANO to provide second required response Page15 ef 22

_._.____7- _ _

TAC NUMBER: MA1805 UNrT: 2 ACTION: ANO COGNIZANTINDIVIDUAL: Mosher,N TrTLE: GL 98 01 Y2K Pa=dina== of Ca==a- Systems at ANO TASK: GL 98 01 OUTAGE RELATED7: No WIDCH OUTAGE:

SUMMARY

STATUS: By letter dated August 10,1998, the 90 day response to GL 9841 was provided to the NRC. A response confirming our Y2K r=An*== will be submitted by July 1,1999.

ACTION NEEDED: ANO to provide second required response I i

i TACNUMBER: MA1951 UNIT: 2 ACTION: NRC COGN1ZANTINDIVIDUAL: Dosa,J j TrrLE: Review of Methodology for SG Tube Integrity TASK: OtTTAGE RELATED7: No WIUCH OUTAGE:

SUMMARY

STATUS: The NRC staff has opened this TAC item at the request of EMCB branch of NRC. No request for information has been provided to ANO, to date.

ACTION NEEDED: NRC to provide request for information ]

TACNUMBER: MA2022 UNTT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Dosa,J TrrLE: ANO 1 Second Intem! ISI ReliefRequests  !

TASK: OITTAGE RELATED7: No WIGCH OUTAGE:

SUMMARY

Dunng the preparation of the IR13 Owner's Activity Report (OAR-1) for the third penod of ANO. f l's 2nd interval as required by ASME Code Case N-532 and 10CFR50.55a, it was discovered that the inspection period distribution requirements had not been met fbr certain ASME Sectnen XI Code Examination Categories. The interval percentage requirements have been met for the 2nd Ten year Inservice fa=:-*:aa Interval, i.e.,100%. In addition, during 2nd interval, sixty components received ev==ia=' ions that were less than the 100% examination volume as required by ASME Section XI 80/W81 and three components received examinations that were lest than the l 90% examination volume as ' required by Code Case N-460.

STATUS: On June 1,1998, ANO submitted two relief requests from the second ISI interval which ended on June 1,1997. RR 1-98 001 concerns period inspection distributions and RR 14 002 discusses l limited exams due to geometric interferences, ACTION NEEDED: NRC approval  !

TACNUMBER: MA2023 UNrra 1 ACTION: NRC COGN1EANTINDIVIDUAL: Dosa, J I TTTLE: ANO-1 Risk-Based ISI TASK: OUTAGE RELATED7: Yes WIUCH OUTAGE: 1R15

SUMMARY

'Ibe ANO-1 Pilot Application for reducing ISI !=F =5! is a partial smpe approach for Class 1, i Category B J welds per IWB-2500. This pilot has been submitted under Code Case N-560. ' Itis  !

approach involves p;rforming a consequence evaluation and a degradation mechanlem evaluation for determining risk sir *== cf a piping system segment. NRC approval is scheduled for June 30,1999. [This is identified as one of the NRC initiatives Mentified in COMSECY-98 024)

STATUS: On Joce 3,1998, ANO 1 submitted a' request to use Code Case N 560 for risk infonned inspections of B J piping welds. This is an accepted NRC pilot plant application. NRC targeted review and approvalis July 1999.

ACTION NEEDED: NRC approval Page 16 of 22

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TACNUMBER: MA2244 UNrt: 2 ACTIhM: NRC COGNIZANTINDIVIDUAL: Bennett, S TITLE: ANO 2 PPS USQ $0.90 TASE: OUTAGE RELATED?: Yes WHICH OUTAGE: 2R13

SUMMARY

Entergy had identi5ed that a failure of a DC bus (FODCB) could result in va=?41e plant response as discussed in ANO-2 LER 96 0441 (2CAN019701) dated January 30,1997. Since FODCB with an masun=f parandary plant trip, results in the loss of offsite power, loss of poner to one division of ESFAS could have resulted. De power division failure includes the ae-energization of one pair of vital instrument buses (VIBs) that could have rendered two measurement channets inoperable with a channel in indennit e bypass The failure of two channels of vital instrument power was not fully evaluated in the PPS design bases for each ESFAS fhnetion. The proposed change will modify the ESFAS portion of the ANO-2 PPS design l to ensure that it will have the redundancy and iW sufBeient to assure that (1) no smgle failure results in loss of the protection function, and (2) removal fan se vies of any compouest or channel dcas not result in loss of the required minimum i.0..i- f required by the ANO 2 Technical Speci5 cations. However, the failure modes for evaluated +:dpment in the ANO-2 Safety AnalyU Report (SAR) do not include daiob. don of either pair of VIBs caused by a FODCB. Even though, the proposed modification does not, in itself create a new rialfunction; the proposed SAR change Ari a malfunction of a different type than previously reporte.1in the SAR and therefore, meets the criteria of 10CFR$0.59 (a)(2). whereby NRC review and soproval under the requirements of 10CFR50.90 is being requested.

STATUS: En;:rgy met with members of the NRC Staff on October 14,1998, to discuss the proposed PPS modifications and how the mod:Acations correct the ESFAS response portion of PPS. Based on that meeting, additional information was identified which was necessary to clarify the Entergy Operations' June 30,1998, submittal. This information is attached foryour review. S#+4= dy, ANO also notined the NRC that the PPS modanicaiton is being deferred until the following 2R14 outage. The followup information and the formal noti 5 cation of deferral was provided to the NRC in letter dated November 23,1998 (2CAN119805). On February 17,1999 the NRC s'affissoed the SE on approval of the USQ as A=ad-nf 201 to the ANO 2 OL.

ACTION NEEDED: NAC Closure i

TAC NUMBER: MA2396 UNIT: 2 A CTION: ANO CCGNIZANT INDIVIDUAL: Boyd,D j

- TrrLE: ANO-2 SG replacement Pre-Application Meetings and Preparations TASE: OUTAGE REIATED7: No WNICH OUTAGE:

SUMMARY

ANO-2 will be replacing steam generators at 2R14 wheduled to commence in %M 2000.

De SGs will be increased in size and number of fahes. This will allow for fhture power uprate to 107.5% power in 2002. As a result of the chang: inag.amers several tarhnical spacinemians will require modification. De ANO 2 containment design pressure will need to be increased and i the addition of an MSIS on high containwnt pressure will be added. All technical specification ,

changes are targeted for 5-d-r 1999 to allow the NRC staff 12 months review period. l l

STATUS: ANO is gas h in the advanced scoping of TS changes. Initial TS changes are expected in May 1999.

ACTION NEEDED: ANO to provide TSCRs for NRC review 1

Pass 17 of 22

• ' " ' ACTION: NRC COGNIZANT DIDIVIDUAL: Mosher,N TAC NUMBER: MA2397 UNIT: 2 TITLE: ANO-2 Service Water to Spent Fuel PooIImk TASK: GL 90 05 OUTAGE REIATED7: No WIUCH OUTAGE:

SUMMARY

During routine operator rounds on June 12,1998, a 5 drop per minute leak in a 1" drain line ham the spent fbel pool heat exchanger (2E 27) y==!= to thr. Arkansas Nuclear One, Unit 2 (ANO-2)1oop 2 service water (SW) header was coserved. GL 90 05 requires that Code relidle sought whhin 30 days for class 3 piping if Code repair cannot be perferined.

STATUS: By letter dated July 13,1998 (2CAN079802), ANO requested w. y relidper GL 90 05 to allow a non code repair of piping in the ANO 2 loop 2 service water system. A listing of SW piping segments that reliefis being requested was sent to the NRC on January 21,1999 (OCAN019902). His submittal also included a sentement that the effected piping segment was replaced in 2R13'which would be adequate for N'RC closure of this action.

ACTION NEEDED: NRC Cloeme TAC NUMBER MA239g UNTT: 2 ACTION: NRC COGNIZANT INDIVIDUAL: Cooper,R TITLE: VaricaNO-2 TS Bases Changes TA3K: TSCR2-9442 OUTAGE RELATED7: Ne WIGCH OUTAGE:

EUMMARY: ,

I STATUS: By leuer dated July 13,1998 (2CAN079803), ANO submitted a Unit 2 TS Bases change request that modifies the bases for specifications 2.1.2,2.2.1,3/4.2.1, and 34.6.3. These changes have been reviewed IAW with 10 CFR 50.59 and concluded that an unrevi:wed safety question is not involved.

ACTION NEEDED: NRC to issue these pages .

TAC NUMBER: MA2401 UNIT: 1 ACTION: NRC COGN1ZANT F4DIVIDUAL: Mosher, N TITLE: Open Equipn.ent Hatch During Core Alterations 1 TASK: TSCR 0-96 04 OUTAGE RELATED7: No WIUCH OUT/.GE:

SUMMARY

Allow the equipment batch to remain open during core alteral'cas.

STATUS: On June 26,1996 (OCAN069601), ANO submitted a TS chants request to allow tle equipment hetch to remain open during core alterations. ANO requested the change prior to IR13. %e techilcal reviewer visited the ANO sitejust prior to 1R13 in order to gain additional insights into how this change would be implemented. De Staff did not approve this change in support of 1R13. By letter dated November 19,1996 (0CNA119609), the NRC informed ANO that they ilo not plan to act on this request until the shutdown operations rule is final and ranammendad that we consider withdrawing the application at this time. Entergy Operations would like this TAC item to renwin open and action to be taken by the NRC. De bases of the subject technical specification 4 addresses ibel handhng accidents only and not a loss of decay heat removal event. On %+ 2- E 30,1998, the shutdown rule was incorporated into the draft revision to the maintenanr* rule.

Entergy Operations requests the NRC review this change. Based on converstions with the ANO 1 Project Manager, the Staff requested additional information be added to the TS pages. The revised TS pages were submitted on February 24,1999 (OCAN029908).

ACTION NEEDED: NRC to issue TS n=*ad=**

Page 18 of 22

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TAC NUMIER: MA2402 UMTT: 2 ACTl!N: NRC COGNIZANT DfDIVIDUAL: Mosher, N TTTLE: . Open Equipment Hatch During Core Alterations TASK: TSCR0-9644 OUTAGE RELATED7: No WIDCH OUTAGE:

l

SUMMARY

Allow the equipment hatch to :anain open during core alterations.

2TATUS: On June 28,1996 (0CAN059601), ANO submitted a TS change request to allow the equiparat hatch to remain open during core alterations. ANO requested the change prior to 1R13. The

eachnical reviev.es visited the ANO sitejust prior to 1R13 in order to gain a61stior al insights into how this change would be implemented. The Staff did not approve this change in support of IR13. By letter dated November 19,1996 (OCNA119609), the NRC informed ANO that they do not plan to act on this request until the shutdown operations rule is final and recommended that we consider withdrawing the application at this time. Entergy Operations would like this TAC item to remain open and action to be taken by the NRC. The bases of the subject techmcal =;=t"==^!==

addresses fuel k=nio, accidents only and not a loes of decay heat removal event. On i;^ " + -

30,1998, the shutdown rule was incorporated into the draft revision to the malatea- a rule.

Entergv Operat;ons requests the NRC review this change Based on converstions with the ANO 1 Project Manager, the Staff requested additional irformation be added in the TS pages. The revised TS pages were submittad an February 24,1999 (OCAN029908)

ACTION NEEDED: NRC to issue TS amendmem4 TACNUMBER: MA2403 UNIT: 2 ACTION: NRC COGNIZANTD(DIVIDUAL: Cooper,R COGNIZANTINDIVIDUAL: Szabo, C I T ITLE: ANO 2 Design FeaturesTSCR TASK: TSCR 2-9643 OUTAGE RELATED7: No WHICH OUTAGE:

SUMMARY

TS change to convert .he design features section of the ANO-2 TS %. ansistent with the a revised armedard TS.

STATUS: By letter dated August 23,1996 (2CAN089609), Entergy Operations submitted a TS change to convert the design features section of the ANO-2 TS to be consistent with the revised standard TS.

This TS change will also correct' errors that are in the current TS. Approval of this request will Ai-iaa* future amendment requests for this section. This TAC item was previously entered as M96480 which was closed tothis one.

ACTION NEEDED: NRC to issue as an amendmas4 TACNUMBER: MA2494 UNTT: 1 ACTION: NRC COGNIZANT INDIVIDUAL: Szabo, C TTTLE: ANO-1 NaOH TSCR TASK: TSCR 1-9544 OtTTAGE RELATED?: No WHICH OtTTAGE:

i

SUMMARY

Entergy Operations plans to propose change to preclude a potential for post-14CA reactor building sump / spray solutions to have pH values higher than those evaluated for EQ .

considerations and hydrogen generation rates. Tbc proposed change revises the concentration )

limits and volume requirements specified for the NaOH tank.

rTATUS: On August 6,19981CAN089801), the proposed TS change was transmined to NRC. j ACTION NEEDED: NRC to issue TS Amendmaar l

Page 19 of 22

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' " ' ' TACNUMBER: MA2495 UNIT: 2 ACTION: NRC COGNtEANTINDn1 DUAL: Cooper, R 1 TITLE: ANO-2 CEA Position Indication and Centalment Penetratica Cwrcurrent Table Relocation TSCR l TASK: TSCR 2-91-26 OUTAGE RELATED7: No WHICH OITTAGE:

SUMMARY

STATUS: By letter dated August 6,1998 (2CAN089802), ANO-2 submitted this TSCR to modify the CEA position indscation channel requimnent to be consistent with the STS: This change also includes the relocates the CNDdT penetration overcurrent devices bom the TS tc . ptant procedures IAW GL 9108. .

ACTION NEEDED: NRC to issue as an ==wnd=wat TAC NUMBER: MA3588 UMTT: 2 ACTION: NRC COGNIZANTINDn1 DUAL: Boyd, D TTTLE: Request to Use Code Cases 2142-1 and 2143 1 for SG Pepla==wat TASK: OUTACE RELATED?: No WHICH OUTAGE:

j l

SUMMARY

Entergy is in the process of fabricadng replacement steam generators for innallation on our ANO-l 2 facility. 'Ibe replamnant steam generators will be using Alicy 690 clad material which has teen proven to be more corrosion resistant than Alloy 600 for } OS applications. The application of Nickel Chromium-Iron (Ni Cr-Fe) welding materials simils :o Alloy 690 is necessary in the fabrication and installation of the replacement steam generators. Code Case 2142 1 apannes the alternativr. rule requirements which may be applied to grouping UNS N06052 Ni-Cr-Fe weld Aller meta! And Code Case 2143 1 speci6es the alternr.tiw mie requinments which may be applied to grouping UNS W:%152 Ni-Cr-Fe welding electrodes. "1tese welding materials provide a better

, weld interface with Alloy 690. The original Code Cases 2142 and 2143 were appmved by ASME in 1992; and were subsequently revised in June 1995 with no substantive change.

l FTATUS: In accordance with the provisions of 10CFR50.55a(s)(3), (Entergy requested approval to use ASME Code Cases 2142 1 and 2143-1 on the Reactor Coolant System for ANO-2 as d=mmaad in letter dated %-- -- *-:i 9,1998 (2CAN099804).

ACTION NEEDED: NRC approval TACNUMBER: MA4367 UNTT: 1 ACTION: NRC COGNIZANTINDIVIDUAL: Mosher,N ,

TTTLE: QAMO Submittal l TASK: OITTAGE RELATED7: No WHICH OUTAGE:

l

SUMMARY

STATUS: On November 9,1998 (0CAN119807), Entergy Opertalons prmided Revision 20 to the Quality Assurance Manual Operations (QAMO). This revision will remain in effect until implementation of the common Quality Assurance Program Manual (QAPM) which was approved for implementation on April 31,1999.

ACTION NEEDED: NRC closure .

i

% 20of 22

TACNUMBER: MA4368 UNIT: 1 ACTION: ANO COGNIZANTINDIVIDUAL: Szabo, C TITLE: .m.tal*stive Controls Section changes to support EOI common QAPM effort TASK: TSCR0-98 04 OUTAGE RELATED?: No WIDCH OUTAGE:

SUMMARY

Incorporates changes in the Adinin Controls sections necessary to support the common QAPM. In ,

addition, several cleanup items have been iw..eed which replace position tiles with ihnetional responsibilites, revise the content of the monthly operating reports and relocate special reports samar4ata4 with fire protection on ANO 1 from the TS. Some of these changes are required to I

allow implementation of the QAPM in Apri',1999.

STATUS: 11/24/98 Submitted proposed TS' change revising Admin t.ontrols to allow incorporation ofEOT common QA Program Manual. Also included changes associated with GL 88-12 (R-Wa+6 of Fire Protection Requinmeats), GL 88 *6 (Position Titics and Functional Descriptions) and GL 97- ,

02 (MORlevel of actail). l l

By letter dated 2/3/99, NRC requested additional iaformation to support requested changes. ANO to respond within 30 days.

ACTION NEEDED: ANO to prmide submittal TACNUMBER: MA4381 UNIT: 2 ACTION: NRC COGNIZANT INDIVIDUAL: Mosher, N TrrLE: QAMO Submittal TASK: OUTAGE RELATED?: No WIDCH OUTAGE:

SUMMARY

2TATUS: On November 9,1998 (OCAN119807), Entergy Opertalons provided Revision 20 to the Quality j Assurance Manual Operations (QAMO). This revision will remain in effect until implementatiaa  !

of the common Quality Assurance Program Manual (QAPM) which was approved for implementation on April 31,1999.

ACTION NEEDED: NRC closure l i

TAC NUMBER: MA4382 UNFF: 1 ACTION: ANO COGNIZANTINDIVIDUAL: Szabo, C TITLE: Administrative Controls Section changes to support EOl common QAPM effort TASK: TSCR 0-98 04 OUTAGE RELATED?: No WIDCH OLTTAGE:

SUMMARY

Incorporates changes in the Admin Controls sections necessary to support the common QAPM. In addition, several cleanup items have been incoporated which replace position tiles with funcuonal responsibilites, revise the content of the monthly operating reports and relocate special reports  ;

associated with fire protection on ANO-1 from the TS. Some of these changes are required to allow implementation of the QAPM in April,1999.  !

FTATUS: 11/24/98 Submitted proposed TS change revising Admin controls to allow incorporation of EOI common QA Program Manual. Also included changes associated with GL 8812 (Relocation of Fire Protection Requirements), GL 88 06 (Position Titles and Functional Descriptions) and GL 97-02 (MORlevelof detail).

Byletter dated 2/5/99,NRCi%d additional information to support reg stedchanges. ANO to respond within 30 days. ,

ACTION NEEDED: ANO to provide mih=ittal Page 21 eC 22 p , e ~ ==we ee- - * ' - * .__

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TAC NUMBER: MA4433 UNTT: 2 ACTION: None COGNIZANTINDIVIDUAL: Boyd,D

' TITLE: ANO-2 RSG Code Case 593 TASK: OUTAGE RELATED7: No WIGCH OUTAGE:

SUMMARY

STATUS: In accordance with the provisions of 10CFR50.55a(aX3). (Entergy requested approval to use ASME Code Case N 593 regarding replacement steam generator nozzle-to-vessel welds once each ;

ten year inspection interval for ANO-2 as discussed in tener dated October 22,1998 l GCAN109803). j I

ACTION NEEDED: NRC approval l

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Upcoming ANO Submittals 03/01/1999 Title /Sununary Cognisant Individual Espected Date ANO 2. Revise Deflaltion of" CORE ALTERATION" to the deflaision Szabo,C 10/1/99 costalmed la NUREG 1432, "CE ISTS" for use la 2R14.

ANO-1 ITS Submittel Szabo,C 10/15/99 Conversion submittal for ANO 1 to the format ofNUREO-1430.

ANO-1IST Third 10 YearInterval Dona,J 10/5/99 ANO-1/2 TS Resetor Coolmat Pump Flywheeilaspection TSCR Dosa,J 12/1/99 Delete requirements to perform ISI of the RCP flywheel inspechons.

Generic Ietter 87-02 Selsmie Qualifiention of Mechaalcal and Electric Mosher,N 3/12/99 Equipment (SQUG)

In February,1987, the Nuclear Regulatory Commission (NRC) issued Generic Istter #87 02. The impact of the generic letter on ANO is that it will be necessary to reevaluate the seismic adequacy of certain equipment identified as ' essential" per USI A-46 criteria. An owner's group, Seismic Quahfication Utility Group (SQUG), was formed during the initial stages of USI A-46 development to demonstrate that past earthquake experience data can be used to verify the seismic adequacy of equipment at nuclear power plants. The elTorts of the SQUO resulted in the NRC agreeing (in Generic letter #87 02) that the use of past canhquake %hce data is an acceptable method of verifying the seismic adequacy of equipment in operating nuclear power plaats and can be used as a basis for resolving USI A 46. With NRC endorsement and consent, the SQUG has developed generic resolution criteris and guidelines to be used in the implementation of the requirements of Genenc letter # 87 02 (Generic Implementing Procedures, GIP). The GIP was submitted in the Spring of 1988. In a letter dated March 11,1991, the NLC provided approximately 70 comments on Revision 2 of the GIP to SQUO.

IFEEE for Esternal Events (GL 88-20 Supphonent 4) Mosher,N 3/12/99 Supplement 4 (IPEEE) to the generic letter was issued on June 28,1991. This supplement required a response that describes the ANO proposed program within 180 days of receipt. In letter OCAN129101, dated December 19,1991 ANO =-+ A4 to submit e schedule within 120 days following receipt of the SQUO OIP SSER. The OIP-2 SSER was received on May22,1992.

RAI on Pressure Lecking sad Thermal Blading of Gate Valves Beruwtt, S 3/15/99 By letter dated October 16,1995 (OCAN109509), ANO responded to the generic letter. A screening evaluation and operability basis of safety related power operated gate valves potentially susceptible to pressure locking and thermal binding had been completed. An additional response was planned to be submitted on February 13,1996, describing further completed analyses, corrective actions to ensure identified susceptible valves are capable of performing their intended safety function, and a completion schedule for any plarm d equipment or procedural modifications. On February 13,1996,Entergy Operations submitted the 180 day response which docenents the results of evaluations performed for pressure lo: king and thermal bindMg per OL 95 07 for 214 Unit I and Unit 2 safety-related power operated gate valves (i.e., all safety-related power operated get: valves at ANO). A total of 56 valves for bcth ANO units combined were identified as potentially susceptible to binding and locking. A total of 9 valves for both ANO units combined were L.. Led to be susceptible to pressure locking.

Appendis R Eseenption for Hot Shorts Cooper,M 3/20/99 ANO is curwndy addressing an issue with the NRC egion and Staff regarding multiple hot shons of the ANO 1 HPI system. The NRC has corduded that a fire induced cable damage of multiply circuits will prevent the safe shutdown of the unit. ANO believes that this scenano is beyond the licensing basis ofANO 1 and is extremely unlikely. If the NRC concludes that this action is in violation ofAppendix R ANO will request that this event be considered for relief as an exemption.

GL 96 05 MOV Capability Periodie Veriflestion Benett,S 3/20/99 Entergy Operations developed a periodic verification program that wi!! er.sure long term design basis capability of the safety releasd MOVs within a scope of OL 96 05. This program is documented in company procedure DC 110,' Periodic Verification," which became effective January 27,1997.

ANO 1 Battery Requirements TSCR Szabo,C 3/25/99 Revise the battery surveillance require nents Page 1 of 3

e *. m TitintSumunary Cogelsa tladivkIInl Espected Deb ANO 2 TS Change ASewlag RFS laoperable Fumetions to Be Placed la Servlee Scheule,R 3/25/99 For FFS lagle Matris Testing Testing a matrix logic with one inoperable channelin trip will result in the matrix ladder having two trip signale present, giving us a high degree ofrisk. Matrix can not be tested with an inoperable channelin bypass. Change w;1".rs, e the ISTS 3.0.5 allowenee to retum an inoperable system to service under adrninistrative controls to perform testing to demonstrate its operabihty or the 4 "'i ofother equipment. The eBowance will only apply to the RPS for Cycle 14 until the rrud eyele outage. A nwe permanent fix may be considered later. The next matrix to be affected is scheduled for two weeks from now (2/25/99). The120 1.0.2 sutension would allow about 30 more days.

ANO 1IWL Relief Request . Bennett,S 3/26/99 ANO 2 IWL Relief Request Bennett,S 3/26/99 ANO 1. Revise ESAS Inw RCS Pressure Setpoint Szabo,C 3/30/99 Reviss ESAS Iow Pressure Trip setpoint to account for additional instrument uncenamties. The current TS setpoint does not include the effects ofinsulation resistance on instrunwnt accuracy or the effects of steam generator tube plugging nn the ameE breakIDCA analyna ANO 1/2 Centalement/ Tendon Inspecties TSCR Szabo,C 4/1/99 Revise sentamment/ tendon inspections to reflect the requirements of Sections IWE and IWL of section XI of the ASME code.

ANO 2 Design Features TSCR Szabo,C 4/1/99 TS change to convert the design features section of the ANO 2 TS to be consistent with the revised standard TS.

ANO-2 RSG COLR TSCR Bowd.D 4/1/99 302 RSG ESFTSCR Boyd,D 4/1/99 ANO-2 RSC Flow TSCR Boyd,D 4/1/99 I

ANO 2 RSC HU/CD TSCR Boyd,D 4/1/99 j ANO 2 RSG Insp TSCR Boyd,D 4/1/99 ANO 2 RSC FT TSCR Boyd,D 4/1/99 ANO 2 RSC RPS TSCR Boyd,D 4/1/99 ANO 1 ARC for Outside Diameter laterErnauler Attack in the Upper Tube Doen,J 4/15/99 Sheet The proposed amendment request establishes an attemate repair criteria (ARC) fer the upper tubesheet region of the ANO 1 steam generators. The basis for this change is a report prepared for the Babcock and Wilcox Owners Group (B&WOG) BAW 10226F, "Ahernate Repair Criteria For Volumetric Outer Diameter Intergranular Attack In The Tubesheets Of Once Through Steam (hnerators? Entergy Operations has chosen to provide the lead plant submittal for the B& WOO for the use of the ARC.

ANO 1 Tube End Cracklag ARCTSCR Dose,J 4/15/99 Delete Requiresnents for FASS Boyd,D 4/30/99 Page 2 of 3

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Tide /Sumunary CogelsantladMdral Espected Date ANO 1 Rerou and Multiple ReroB TSCR Dosa,J 5/18/99 ANO Rene Shutdown Coollag Flow Limle to Account for lastnanent Szabo,C 6/1/99 Uncertalaties l

l Currently,the 2000 spm limit of TS 3.1.1.3 and 3.9.8.1 do not include instrument uncertainties. Due to vortexing concerns at high flow rate, evalaste reducing the required flow so that when instrument enoertainty is included, the indiated Dow can be 2000 spm. Desired for 2 Rid, Committed to U2 Ops for 2P99.

50.12 Esemptions Still la Effect for License Renewal Perted Mosher,N 6/15/99 ANO 1 Appendiz R Clariflestion for MU Pump Roesa Lube 00 Pumps Mosher,N , 6/15/99 j ANO-1 Bases Change to Incorporate Statistical Core Deelga Mosher,N 6/15/99 Change TS bases for specificahani 2.1 to include the statistical core design methodology for calculating r, acceptab'e DNBR design j limit.

ANO 21400 Sleeves TSCR Dosa,J 6/30/99 This change is to revise TS 4.4.5 and its =Waw bases to allow the use of1400 steam generator tube sleeves.

Revise ANO-1 and ANO 2 specified curie content for Waste cas Decay Taalm Szabo,C 7/1/99 Based upon calculations the noble gass limits of 300,000 curies was found to be excessive morew+.ete values of78,782 curies for ANO.1 and 82,400 curies for ANO 2 should be specifud. Admis istrative controls are in place.

ANO 1 leak Detection lastrumentstion TSCR Bennett,S 8/15/99 Change Ieakage Detection Systerns specification to require either the gaseous or particulate morutor in service, and allow opershon for up te 30 days provided grab samples or an RCS inventory balance is performed once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ANO-1 Purge Valve TSCR Mosher,N 9/11/99 l

t Page 3 of 3

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