|
|
| (2 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 09/27/1984 | | | issue date = 09/27/1984 |
| | title = Confirms Info Discussed at 840911 Meeting W/Licitra & Kubicki in Bethesda,Md Re Revised Fire Protection Evaluation Rept Included in Amend 13 to Fsar.Fsar Will Be Amended to Address Issue Re Fire Dampers | | | title = Confirms Info Discussed at 840911 Meeting W/Licitra & Kubicki in Bethesda,Md Re Revised Fire Protection Evaluation Rept Included in Amend 13 to Fsar.Fsar Will Be Amended to Address Issue Re Fire Dampers |
| | author name = VAN BRUNT E E | | | author name = Van Brunt E |
| | author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR | | | author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| | addressee name = KNIGHTON G | | | addressee name = Knighton G |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)ACCESSION"NBR:801 FACILiSTN~50~528 | | {{#Wiki_filter:REGULATOR INFORMATION DISTRIBUTION TEM (RIDS) |
| 'STN 50 529 STN~50 530 AUTH INANE;VAN,BRUNTgE',K
| | ACCESSION "NBR:801 0010207 DOCRDATE: 84/09/27 NOTARIZED;; NQ DOCKET FACILiSTN~50~528 "Palo Verde Nuclear StatianR Unit li Ar)zona, Publi 05000528 |
| ~RKC I P~NAME.KNIGHTlONi G I 0010207 DOCRDATE: 84/09/27 NOTARIZED;;
| | 'STN 50 529 Palo Verde, Nuclear Stations Unit 2i Ar izona Publi'5000529 STN~50 530 Palo Verde Nuclear Stationi Unit 3g Arizona Publi 05000530 AUTH INANE; AUTHHDR AFFILIATION VAN,BRUNTgE',K~ Arizona Public Service -Co ~ |
| NQDOCKET"Palo Verde Nuclear StatianR Unit li Ar)zona, Publi 05000528 Palo Verde, Nuclear Stations Unit 2i Ar izona Publi'5000529 Palo Verde Nuclear Stationi Unit 3g Arizona Publi 05000530 AUTHHDR AFFILIATION Arizona Public Service-Co~RECIPIENT AFFILIATION Licensing Branch<<3 SUBJKCTj'Confirms info discussed, at 840911 meeting w/Licitra-L Kubicki in,Bethesda<MD re'evised fire protection evaluation rept'ncluded-in Amend 13,to FSAR.FSAR will be amended to address"issue re fire dampers, DISTRIBUTION CODE:.BOOED COPIES RECEIVEDgl.,TR J.ENCL P SIZE:'i'..TITLKt Licensing Submittal:
| | RKC I P ~ NAME. RECIPIENT AFFILIATION KNIGHTlONiG I Licensing Branch <<3 SUBJKCTj 'Confirms info discussed, at 840911 meeting w/Licitra -L Kubicki in,Bethesda<MD re'evised fire protection evaluation rept'ncluded -in Amend 13,to FSAR.FSAR will be amended to address"issue re fire dampers, DISTRIBUTION CODE: .BOOED COPIES RECEIVEDgl.,TR J. ENCL P SIZE: 'i'. |
| Fire Protection NOTES)Standardized plant, Standardized plant~'Standardized plantB 05000528 05000529 05000530 RECIPIENT'D GOOK/NAME NRR LB3 BC COPIES LTTR ENCL REC IP IENT ID CODE/NAME LICITRAr E 01'COPIES LTTR ENCL INTERNAL'DM/LFMB IK FII El NRR/DSI/ASB RGN5 EXTERNAL'! | | .TITLKt Licensing Submittal: Fire Protection NOTES)Standardized plant, 05000528 Standardized plant ~ 05000529 |
| AGRS ,NRC;PDR NTIS 07 10: 02" 1 1 ELD/HDS3 EG F K.LPDR-NSIG 06 0$03 05 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL:
| | 'Standardized plantB 05000530 RECIPIENT'D COPIES REC IP IENT 'COPIES GOOK/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB3 BC LICITRArE 01 INTERNAL'DM/LFMB 1 ELD/HDS3 1 IK FII El 07 06 NRR/DSI/ASB EG F K. 0$ 1 RGN5 1 EXTERNAL'! AGRS 10: LPDR- 03 |
| T ,>>'I)'P i g>>'w ll'<<C>h>f'>>,<<)'hh f'4 f 4 K>(y>>4 4 4>II r I'I W,ll rl ll l l"" 4'4 wc 4'>Q<<4>r f,'4~r I, T>>''4>~I'1 lrrl'/w ll'l 4<<" 4 I'g (wf 4, i,lff>r rlr'fl,rr>r,l>>>f f I'4"'>I<<<<''>ll I, 4<<>><<>>>hf rr" f''I w'h I~T I.w I<<T<<I(hr f 0 l<<" l 4>4 e'I" E Tf'f f p,f 4 If jl jf w>>I>>il r>>f 4.4 44 f.f I<<r%f'll T><<fT f fl I>><<>fJ>lyly@4J<<rr<<rg f lip 4<<~j h 4 Arizona Public-Service Company P.O.BOX 21666~PHOENIX, ARIZONA 65036 ANPP-30680-EEVBJr/TFg/DKN September 27, 1984 Director of Nuclear Reactor Regulation Attention: | | ,NRC; PDR 02" NSIG 05 NTIS TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL: |
| Mr.George Knighton, Chief Licensing Branch No.3 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | |
| | T f 4 f,'4 T>>'' 4> ~ I |
| | ,>>'I) 'P C>h> f 4 K >(y>> 4 4 >II l"" 4'4 wc r 4'>Q<<4 >r |
| | ~ r I, i g >>' ' |
| | w ll << ' |
| | >>, <<) 'hh f '4 W,ll rl ll l I'I lrrl '/ |
| | '1 w ll'l 4 <<" 4 I ' |
| | g ( |
| | i,lff >r '> I<<<< 4<<>><< >>>hf rr" f''I wf 4, rlr'fl,rr > r,l>>>f f '> ll I'4" w'h I I, |
| | ~T I. w I<<T E Tf' f p,f |
| | << I(hr f 0 l<<" l 4> 4 e'I" f 4 If jl jf w>> I >> il f 4.4 r>> 44 f.f r% f'll I<< |
| | T fl |
| | ><<fT f I |
| | ~ h |
| | >> << j lyly@ 4J |
| | > fJ > <<rr<<rg f lip 4<< |
| | 4 |
| | |
| | Arizona Public-Service Company P.O. BOX 21666 ~ PHOENIX, ARIZONA 65036 ANPP-30680-EEVBJr/TFg/DKN September 27, 1984 Director of Nuclear Reactor Regulation Attention: Mr. George Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3 Fire Protection Evaluation Docket Nos.STN-50-528/529/530 File: 84-056-026'.1.01.10 | | Palo Verde Nuclear Generating Station (PVNGS) |
| | Units 1, 2 and 3 Fire Protection Evaluation Docket Nos. STN-50-528/529/530 File: 84-056-026'.1.01.10 |
| | |
| | ==Dear Mr. Knighton:== |
| | |
| | This will confirm information discussed with Messrs. Licitra and Kubicki at a meeting held in Bethesda, MD, on September ll, 1984 on an item in the revised Fire Protection Evaluation Report included in FSAR Amendment 13. |
| | FSAR Question 9A.68, item b, and this letter pertain to Fire Dampers. Our response to FSAR Question 9A.68 indicates that, where the damper is mounted on the surface of the wall, the structural steel attaching the damper to the wall and the first duct support will be coated with fire retardant material of a rating equal to that of the wall. |
| | Upon further investigation, it has been found that this specific type of installation occurs only in a few areas with little or no combustible loading, such as HVAC shafts, essential chiller room, corridors or in rooms where automatic fire suppression systems are installed to limit fire severity. |
| | Following is a fire protection evaluation of the areas where surface mounted dampers are installed: |
| | : 1. Control Building |
| | : a. Dampers installed on the interior wall of the HVAC shafts (2 hr shaft w/l-l/2 hr dampers) are exposed to no combustible load. |
| | 8409i7 salao>0207 0500052S pcP PDR ADOCK PDR F |
| | |
| | Q,<V. i> KA,: |
| | ANPP-30680 Page 2. |
| | : b. Dampers installed on the exterior wall of the HVAC shafts |
| | ; are in fire zones with detection and automatic suppression systems (C02 or water). This would, mitigate the effects of fire and limit the heat exposure. The duct supports are seismically designed and therefore are of substantial steel construction. They would withstand a design basis fire with automatic suppression. |
| | : c. There is one surface mounted damper at the 74'evel (essential chiller room) of the Control Building in the 3 hr rated central wall. The equivalent fire severity in this fire zone (No. 1) is less than 15 minutes consisting primarily of charcoal filters located about 40 feet away. |
| | Smoke detection is installed in the room for early warning. |
| | This installation provides reasonable assurance that a fire will not propagate through the wall. On the other side of the damper is a two hour rated concrete soffit containing no combustibles. There is no direct communication with the adjacent fire area. |
| | : 2. Auxiliary Building |
| | : a. Zone 37A corridor, 70 foot level. There is one surface mounted damper in a one hour rated portion of a concrete wall. The fire loading is less than 20 minutes and there is smoke detection installed in the zone for early warning. |
| | Spatial separation on either side of the wall between redundant safe shutdown equipment is approximately 60 feet total, with no intervening combustibles. This installation provides adequate separation and protection of safe shutdown equipment. |
| | : b. Zone 52A corridor, 120 foot level. There is one surface mounted damper in a one hour rated portion of a concrete wall. The combustible loading consists of cable trays (69 minutes) but is protected by an automatic detection and water suppression system. Redundant safe shutdown equipment is also separated by approximately 80 feet to that located in zone 52B. This installation provides adequate separation and protection of safe shutdown equipment. |
| | |
| | 0 I f |
| | J |
| | |
| | ANPP-30680 Page 3. |
| | Based upon the above analysis of fire hazards, equipment separation and fire suppression systems available, the surface mounted dampers in these areas will provide adequate protection without additional fire proofing. The FSAR will be revised in a future amendment. |
| | Very truly yours, E. E. Van Brunt, Jr. |
| | APS Vice President Nuclear Production ANPP Project Director EEVBJr/TFQ/DKN/dh cc: E. A. Licitra D. J. Kubicki A. C. Gehr |
| | |
| | tl 1i |
| | |
| | ANPP-30680 Page 4. |
| | bcc's: |
| | E. E. Van Brunt, Jr. |
| | A. C. Rogers W. F. Quinn W. E. Ide T. F. Quan G. J. Volk J. R. Bynum J. D. Houchen W. F. Fernow R. W. Meyer L. G. Papworth L. Harris K. W. Gross W. G. Bingham (B) |
| | J. R. Schuh (B) |
| | K. Ng (B) |
| | N. E. Baldasari (B) |
| | J. Curry (B) |
| | L. Barbe (B) |
|
| |
|
| ==Dear Mr.Knighton:==
| | -t~ |
| This will confirm information discussed with Messrs.Licitra and Kubicki at a meeting held in Bethesda, MD, on September ll, 1984 on an item in the revised Fire Protection Evaluation Report included in FSAR Amendment 13.FSAR Question 9A.68, item b, and this letter pertain to Fire Dampers.Our response to FSAR Question 9A.68 indicates that, where the damper is mounted on the surface of the wall, the structural steel attaching the damper to the wall and the first duct support will be coated with fire retardant material of a rating equal to that of the wall.Upon further investigation, it has been found that this specific type of installation occurs only in a few areas with little or no combustible loading, such as HVAC shafts, essential chiller room, corridors or in rooms where automatic fire suppression systems are installed to limit fire severity.Following is a fire protection evaluation of the areas where surface mounted dampers are installed:
| | 1 |
| 1.Control Building a.Dampers installed on the interior wall of the HVAC shafts (2 hr shaft w/l-l/2 hr dampers)are exposed to no combustible load.salao>0207 8409i7 PDR ADOCK 0500052S F PDR pcP Q,<V.i>KA,:
| | / |
| ANPP-30680 Page 2.b.Dampers installed on the exterior wall of the HVAC shafts;are in fire zones with detection and automatic suppression systems (C02 or water).This would, mitigate the effects of fire and limit the heat exposure.The duct supports are seismically designed and therefore are of substantial steel construction.
| | p ll}} |
| They would withstand a design basis fire with automatic suppression.
| |
| c.There is one surface mounted damper at the 74'evel (essential chiller room)of the Control Building in the 3 hr rated central wall.The equivalent fire severity in this fire zone (No.1)is less than 15 minutes consisting primarily of charcoal filters located about 40 feet away.Smoke detection is installed in the room for early warning.This installation provides reasonable assurance that a fire will not propagate through the wall.On the other side of the damper is a two hour rated concrete soffit containing no combustibles.
| |
| There is no direct communication with the adjacent fire area.2.Auxiliary Building a.Zone 37A corridor, 70 foot level.There is one surface mounted damper in a one hour rated portion of a concrete wall.The fire loading is less than 20 minutes and there is smoke detection installed in the zone for early warning.Spatial separation on either side of the wall between redundant safe shutdown equipment is approximately 60 feet total, with no intervening combustibles.
| |
| This installation provides adequate separation and protection of safe shutdown equipment.
| |
| b.Zone 52A corridor, 120 foot level.There is one surface mounted damper in a one hour rated portion of a concrete wall.The combustible loading consists of cable trays (69 minutes)but is protected by an automatic detection and water suppression system.Redundant safe shutdown equipment is also separated by approximately 80 feet to that located in zone 52B.This installation provides adequate separation and protection of safe shutdown equipment.
| |
| 0 I f J ANPP-30680 Page 3.Based upon the above analysis of fire hazards, equipment separation and fire suppression systems available, the surface mounted dampers in these areas will provide adequate protection without additional fire proofing.The FSAR will be revised in a future amendment.
| |
| Very truly yours, E.E.Van Brunt, Jr.APS Vice President Nuclear Production ANPP Project Director EEVBJr/TFQ/DKN/dh cc: E.A.Licitra D.J.Kubicki A.C.Gehr tl 1i ANPP-30680 Page 4.bcc's: E.E.Van Brunt, Jr.A.C.Rogers W.F.Quinn W.E.Ide T.F.Quan G.J.Volk J.R.Bynum J.D.Houchen W.F.Fernow R.W.Meyer L.G.Papworth L.Harris K.W.Gross W.G.Bingham (B)J.R.Schuh (B)K.Ng (B)N.E.Baldasari (B)J.Curry (B)L.Barbe (B)
| |
| -t~1/p ll}}
| |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML17313B0991999-10-14014 October 1999
Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing
ML17313B0881999-10-12012 October 1999
Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2
ML17300B3501999-09-29029 September 1999
Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7
ML17300B3551999-09-28028 September 1999
Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl
ML17313B0851999-09-24024 September 1999
Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles
ML17313B0781999-09-20020 September 1999
Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included
ML17300B3331999-09-14014 September 1999
Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3
ML17300B3351999-09-0808 September 1999
Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met
ML17313B0761999-09-0303 September 1999
Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H
ML17313B0731999-08-31031 August 1999
Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML17313B0581999-08-0606 August 1999
Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included
ML17313B0311999-08-0303 August 1999
Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML17313B0431999-07-30030 July 1999
Advises of Listed Senior Mgt Changes That Have Taken Place at Plant
ML17313B0441999-07-30030 July 1999
Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps.
ML17313B0151999-07-20020 July 1999
Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys
ML17313B0091999-07-20020 July 1999
Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1
ML17313B0171999-07-16016 July 1999
Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations
ML17300B3111999-07-15015 July 1999
Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr
ML17300B3141999-07-15015 July 1999
Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790
ML20209G6771999-07-0808 July 1999
Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl
ML17300B2931999-07-0202 July 1999
Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval
ML17313A9951999-06-26026 June 1999
Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants.
ML17300B2831999-06-26026 June 1999
Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl
ML17313A9901999-06-15015 June 1999
Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr
ML17313A9521999-05-24024 May 1999
Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55
ML20206Q3111999-05-18018 May 1999
Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety
ML17313A9311999-05-13013 May 1999
Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload
ML17313A9481999-05-12012 May 1999
Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address
ML17313A9261999-05-0707 May 1999
Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing
ML20206H1931999-05-0303 May 1999
Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl
ML17313A9091999-04-30030 April 1999
Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld
ML17313A9181999-04-30030 April 1999
Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790
ML17313A9191999-04-30030 April 1999
Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422
ML17300B3751999-04-23023 April 1999
Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool
ML17313A9081999-04-23023 April 1999
Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531
ML20205T7421999-04-21021 April 1999
Forwards Partially Withheld Insp Repts 50-528/99-05, 50-529/99-05 & 50-530/99-05 on 990322-26.Determined That Security Program Properly Implemented.Insp Repts Details Withheld (Ref 10CFR73.21)
ML17313B0271999-04-21021 April 1999
Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl
ML17313A9031999-04-21021 April 1999
Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection
ML17313A8971999-04-20020 April 1999
Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections
05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999
Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing
ML17313A8931999-04-14014 April 1999
Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met
ML20205Q0821999-04-13013 April 1999
Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item
ML17313A8901999-04-13013 April 1999
Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing
ML17313A8831999-04-0808 April 1999
Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3
ML20205F3491999-03-30030 March 1999
Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1)
ML17313A8671999-03-24024 March 1999
Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3)
ML17313A8601999-03-16016 March 1999
Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon
ML17313A8551999-03-0505 March 1999
Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17313B0991999-10-14014 October 1999
Forwards LER 99-005-00 Reporting Findings & Corrective Actions Taken as Result of Out of Tolerance MSSV Condition in Unit 1 Which Was Discovered During pre-outage Testing
ML17313B0881999-10-12012 October 1999
Forwards Response to NRC 990831 RAI Re Several Relief Requests That Accompanied Second ten-yr Interval ISI Program Submitted on 980317.Revised Relief Request 6 Is Provided in Encl 2
ML17300B3501999-09-29029 September 1999
Forwards Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7,in Response to NRC RAI Re Proposed Amend to TS 3.8.1 & 3.3.7
ML17300B3551999-09-28028 September 1999
Responds to Aministrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams. Proposed Palo Verde Operator Licensing Exam Schedule & Estimated Number of Applicants Planning to Take Exams Encl
ML17313B0851999-09-24024 September 1999
Requests Approval of Alternative to Repair Requirements of 10CFR50.55a,authorizing Alternative Use of Mechanical Nozzle Seal Assemblies,As Described in Encl,For RCS Hot Leg Instrumentation & Sampling Nozzles for Two Operating Cycles
ML17313B0781999-09-20020 September 1999
Forwards Rev 22 to PVNGS Emergency Plan. Summary Description of Changes,Included
ML17300B3331999-09-14014 September 1999
Forwards MOR for August 1999 & Revised MOR for Jul 1999 for Pvngs,Units 1,2 & 3
ML17300B3351999-09-0808 September 1999
Informs That Repairs to Plant EDG 2A Jacket Water Cooling sub-sys Were Completed & EDG Was Declared Operable on 990903 at Approx 21:45 Mst.Noed Was Not Necessary,Since 72 Hour Completion Time Was Met
ML17313B0761999-09-0303 September 1999
Requests Enforcement Discretion to TS Section 3.8.1, AC Sources - Operating. Enforcement Discretion Would Allow,On One Time Basis,Extension of Completion Time in Required Action B.4 of TS 3.8.2 from 72 H to 108 H
ML17313B0731999-08-31031 August 1999
Informs That RR Bean (License OP-50452-1) Has Been Permanently Reassigned to Position That Does Not Require License & Requests That Individuals License Be Expired Per 10CFR55.55
ML17313B0581999-08-0606 August 1999
Forwards Rev 1 of Changes to TS Bases Implemented Between Aug 1998 & Jul 1999.Insertion Instructions & List of Affected Pages Included
ML17313B0311999-08-0303 August 1999
Submits Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001
ML17313B0441999-07-30030 July 1999
Forwards Comments on Draft NRC Repts Evaluation of AOVs at Us Light-Water Reactors (1999) & Idaho Natl Engineering & Environ Lab Rept (INEEL)EXT-98-00383,Study of AOVs in Npps.
ML17313B0431999-07-30030 July 1999
Advises of Listed Senior Mgt Changes That Have Taken Place at Plant
ML17313B0151999-07-20020 July 1999
Submits Request to Obtain All Data Previously Sent by PVNGS & Currently in REIRS for OLs NPF-41,NPF-51 & NPF-74.Data Is Requested in Electronic Form (Ascii Format) as It Currently Exists in REIRS Sys
ML17313B0091999-07-20020 July 1999
Forwards Requested Calculations Performed to Verify That Increase in Max Radially Averaged Enrichment for Fuel Assemblies from 4.3 Weight Percent to 4.8 Weight Percent Did Not Affect Requirements for TSs 3.7.15,3.7.17 & 4.3.1
ML17313B0171999-07-16016 July 1999
Forwards LER 99-005-00,re Automatic Rt Which Occurred on 990618,following Sensor Failure in Core Protection Calculators.Corrective Actions Described in LER Are Not Necessary to Maintain Compliance with Regulations
ML17300B3111999-07-15015 July 1999
Forwards PVNGS Unit 2 ISI Rept for Eighth Refueling Outage. No Commitments Made to NRC by Ltr
ML17300B3141999-07-15015 July 1999
Forwards Corrected Electronic Files for Individual Monitoring Repts for 1998.Original Electronic Files Were Found to Have Two Administrative Errors,Which Has Been Corrected.Encl Withheld,Per 10CFR2.790
ML20209G6771999-07-0808 July 1999
Forwards Supplemental Info to Confirm That Decommissioning Funding Plans of Public Service Co of Nm for Interests in PVNGS Have Been Reviewed by Nm Public Regulation Commission. Final Order & Recommended Decisions in Case 2742,also Encl
ML17300B2931999-07-0202 July 1999
Submits Withdrawal of Relief 5 for Second ISI Interval for Units 1,2 & 3.Proposed Alternative Is Related to Exam Requirements for Component Supports for Second ISI Interval
ML17313A9951999-06-26026 June 1999
Provides Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants.
ML17300B2831999-06-26026 June 1999
Requests NRC Approval of Proposed Alternative IAW Provisions of 10CFR50.55a(a)(3)(i) to 10CFR50.55a(g) & Requirements of ASME Boiler & Pressure Vessel Code Section XI for Repairs & Installation.Description of Proposed Alternative,Encl
ML17313A9901999-06-15015 June 1999
Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. No Commitments Being Made to NRC by Ltr
ML17313A9521999-05-24024 May 1999
Notifies NRC That Ja Proctor,License SOP-50314,has Been Permanently Reassigned to Position That Does Not Require License.License Should Be Expired,Per 10CFR55.55
ML17313A9311999-05-13013 May 1999
Notifies NRC That Rev 2 to COLR for Unit 2 Remains Applicable Following Recently Completed Unit 2 Reload
ML17313A9481999-05-12012 May 1999
Informs of Change Needed in Order to Update Current Mailing List.Future Mailings for J Horne Should Be Forwarded to Listed Address
ML17313A9261999-05-0707 May 1999
Forwards LER 99-004-00,per 10CFR50.73.LER Repts Findings & Corrective Actions Taken as Result of Unit 2 Out of Tolerance Pressurizer Safety Valve (Psv) Condition Which Was Discovered During Outage Testing
ML20206H1931999-05-0303 May 1999
Forwards 1998 Annual Rept, for SONGS Units 2 & 3 & PVNGS Units 1,2 & 3.SCEs Form 10K Annual Rept to Securites & Exchange Commission for Fiscal Yr Ending 981231,encl
ML17313A9191999-04-30030 April 1999
Forwards Special Rept 2-SR-99-001 Re SG Tube Plugging in PVNGS Unit 2,per TS Reporting Requirement 5.6.8.Complete Results of SG Tube Inservice Insp Will Be Submitted by 000422
ML17313A9181999-04-30030 April 1999
Forwards Electronic File of Individual Monitoring Repts for 1998.Encl Withheld Per 10CFR2.790
ML17313A9091999-04-30030 April 1999
Forwards Proprietary Proposed Test Outlines for Initial License Exams to Be Administered at PVNGS in Aug/Sept 1999. No Commitments Are Contained in Ltr.Proprietary Info Withheld
ML17313A9081999-04-23023 April 1999
Documents 990421 Telcon with E Emeigh,Which Requested Extension for Submitting Next Matl Balance Rept for Pvngs,As Required by 10CFR70.53 & 74.13.Required Info Will Be Submitted by 990531
ML17300B3751999-04-23023 April 1999
Forwards LER 99-003-00,reporting Condition Prohibited by TS 3.7.17 Where Spent Fuel Assembly Was Stored in Inappropriate Region in Spent Fuel Pool
ML17313B0271999-04-21021 April 1999
Forwards Proprietary Epec Pro Forma Cashflow Statement for 1999.Proprietary Info Withheld,Per 10CFR2.790.Affidavit Encl
ML17313A9031999-04-21021 April 1999
Forwards Rev to Relief Request 12 Submitted 990420 to Second 10-yr ISI Interval.Revised Relief Request Discusses in More Detail Actions APS Will Take When There Is Identified Leakage from Bolted Connection
ML17313A8971999-04-20020 April 1999
Requests Use of Alternatives to 10CFR50.55a(g) Inservice Insp Requirements.Proposed Alternatives Are Related to Visual Exam of Bolted Connections
05000529/LER-1999-002, Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing1999-04-19019 April 1999
Forwards LER 99-002-00 Re Findings & Corrective Actions Taken as Result of Plant Out of Tolerance MSSV Condition Which Was Discovered During pre-outage Testing
ML17313A8931999-04-14014 April 1999
Forwards LER 99-003,reporting Condition Prohibited by TSs That Existed When Surveillance Requirement to Verify Essential Chilled Water Sys Valve Positions Was Not Met
ML20205Q0821999-04-13013 April 1999
Forwards Second ISI Interval Relief Request 10 from ASME Section XI & Applicable Addenda Re Visual Exams Performed Subsequent to Repair or Replacement of Component or Alteration of Item
ML17313A8901999-04-13013 April 1999
Forwards LER 98-003-01 Re MSSV as-found Lift Pressures out- Side of TS Limits.Ler Suppl Provides Evaluation Findings from Unit 3 out-of-tolerance MSSVs Conditions Which Were Discovered During pre-outage Testing
ML17313A8831999-04-0808 April 1999
Forwards 1998 Annual Radioactive Effluent Release Rept for Pvngs,Units 1,2 & 3 & Rev 13 to ODCM, for Pvngs,Units 1,2 & 3 IAW TS 5.6.3
ML20205F3491999-03-30030 March 1999
Forwards Proprietary & non-proprietary Info Re Status of Decommissioning Funding for Pvngs,Units 1,2 & 3,per 10CFR50.75(f)(1).Proprietary Info Withheld,Per Requirements of 10CFR2.790(b)(1)
ML17313A8671999-03-24024 March 1999
Submits Info Re Present Levels & Sources of Property Insurance Maintained for Pvngs,Per 10CFR50.54(w)(3)
ML17313A8601999-03-16016 March 1999
Forwards Revised Relief Requests PRR-05,PRR-06 & PRR-11 to Clarify That Proposed Design Flow Testing for Lpsi,Hpsi & Containment Spray Pumps Will Be Performed Using Instruments That Comply with Code Requirements,Per 990226 Telcon
ML17313A8551999-03-0505 March 1999
Requests Proposed Code Alternative IAW 10CFR50.55a(e)(3),as Acceptable Alternative to Requirements of 10CFR50.55a(e)(1), for Installation of in-line safety-related Flow Measurement Instrument in ASME Class 3 Pipe
ML17313A8241999-02-23023 February 1999
Advises That Kp Jarvis,License OP-50287-1,no Longer Needs to Maintain License as Permanently Assigned to Position Requiring No License
ML17313A8111999-02-18018 February 1999
Forwards PVNGS Unit 3 7th Refueling Outage, Which Provides Complete Results of SG Tube Inservice Insp Performed,Per TS 5.6.8
ML17313A8721999-02-16016 February 1999
Discusses Resolution of Generic Safety Issue 171, ESF Failures from Loss-of-Offsite Power Subsequent to Loca. Util Has Low Vulnerability to Loca/Grid Collapse/Loop Scenario
ML17313A7611999-01-22022 January 1999
Forwards PVNGS Unit 3 Inservice Insp Rept Seventh Refueling Outage, Per 10CFR50.55a.Ltr Contains No New Commitments
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17305B0681990-09-17017 September 1990
Forwards Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule. Exam Dates,Anticipated Number of Candidates & Requalification Exam Schedules for FY91-FY94 Also Encl
ML17305B0491990-09-12012 September 1990
Forwards Palo Verde Nuclear Generating Station Unit 2 Steam Generator Eddy Current Exam,Second Refueling Outage Apr 1990.
ML17305B0281990-08-27027 August 1990
Forwards fitness-for-duty Semiannual Performance Rept for Period of Jan-June 1990,per 10CFR26.71(d)
ML17305B0111990-08-15015 August 1990
Responds to Request for Addl Info Re Emergency Lighting,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25. Availability Info Provided in Ref 2,most Appropriate Analysis of Lighting Sys Availability
ML17305B0021990-08-0909 August 1990
Provides Update on Status of Record 546 post-restart Item, Per 900412 Ltr.Record Will Revise Procedures for Analyzing & Disseminating Incident Investigation,Operations & Maint Experience to Appropriate Dept
ML17305A9871990-08-0303 August 1990
Forwards Rev 1 to Abb Impell Rept 01-1658-1815, Emergency Lighting Independent Review, Per Insp Repts 50-528/90-25, 50-529/90-25 & 50-530/90-25
ML17305A9791990-07-31031 July 1990
Forwards, Conceptual Design for Palo Verde Nuclear Generating Station for Diverse Auxiliary Feedwater Actuation Sys (Dafas) for Review.Schedule of Implementation as Indicated
ML20056A4161990-07-31031 July 1990
Forwards Revised Security Plan Implementing Procedures.Encl Withheld (Ref 10CFR2.790)
ML17305A9831990-07-27027 July 1990
Requests Temporary Waiver of Compliance from Limiting Condition for Operation 3.6.3 to Allow Corrective Maint to Be Performed on Main Feedwater Isolation Valves by Extending Allowed Outage Time to 12 H Instead of 4 H
ML20055J2671990-07-25025 July 1990
Forwards Info Constituting Decommissioning Financial Assurance Certification Rept,Per 10CFR50.33(k)(2) & 50.75(b)
ML17305A9771990-07-25025 July 1990
Forwards Status of Corrective Actions to Min Multiple Control Element Assembly Drop Events at Plant.Insp of Insulation Coils & Replacement of Defective Coils for Units 1 & 2 Completed
ML20055J1711990-07-25025 July 1990
Forwards Certification of Decommissioning Financial Assurances for Plant,Per 10CFR50.75(b) & 50.33(k)(2)
ML20055J1031990-07-25025 July 1990
Forwards Certification of Decommissioning Financial Assurances
ML17305A9411990-07-20020 July 1990
Forwards Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount.
ML17305A9431990-07-17017 July 1990
Forwards Rev 1 to Palo Verde Nuclear Generating Station Annual Radiological Environ Operating Rept for 1987. Rev Results from Internal Review Bu Nuclear Safety Group & Audit Performed by Radiation Protection Stds
ML17305A9601990-07-13013 July 1990
Forwards Preliminary Response Re Justification for Continued Operation of Fire Protection Sys Equipment,Per Insp Repts 50-528/90-25,50-529/90-25 & 50-530/90-25
ML17305A9331990-07-12012 July 1990
Discusses Util Compliance w/fitness-for-duty Program Implementation.Lab Specialists,Inc Audited & Monitored W/ Satisfactory Results.Ltr of Agreement Has Been in Place Since 900202
ML17305A9391990-07-0909 July 1990
Forwards Endorsement 44 to Maelu Policy MF-116 & Endorsement 62 to Nelia Policy NF-266
ML17305A9341990-07-0909 July 1990
Submits Results of 900514-18 NUREG-1220 Audit,Per NRC 900608 Request,Per Insp of Plant.Remaining Licensed Operators Found to Be in Conformance W/Medical Exam Requirements of 10CFR50.55
ML17305A9151990-06-29029 June 1990
Forwards Emergency Lighting Failure Data Update,Per 900621 Request
ML17305A9061990-06-26026 June 1990
Suppls 891114 Response to Violations Noted in Insp Rept 50-528/89-16.Application for Amend to License NPF-41 Will Be Submitted in Oct 1990 to Permit Lower Flow Rate for RCS & Shutdown Cooling Sys
ML17305A9111990-06-25025 June 1990
Responds to Generic Ltr 90-04, Status of Implementation of Generic Safety Issues.
ML17305A9081990-06-25025 June 1990
Forwards Schedule Reiterating Util Plans for Implementation of USIs A-9 & A-44 & Provides Current Forecast Refuel Dates
ML17305A9051990-06-25025 June 1990
Forwards Endorsement 45 to Maelu Policy MF-116 & Endorsement 63 to Nelia Policy NF-266
ML17305A9121990-06-24024 June 1990
Forwards Discharge Test Voltage Curve,Per 900623 Request for Completion of Emergency Lighting Exide Power Supply Prior to Entry Into Mode 2
ML17305A9171990-06-24024 June 1990
Confirms Compliance W/Agreed Upon Course of Action for Restart of Facility as Outlined in 891224 Ltr & Completion of Items Contained in Restart List Provided as Attachment to 900111 Ltr
ML17305A8961990-06-20020 June 1990
Responds to NRC 900521 Ltr Re Violations Noted in Insp Repts 50-528/90-12,50-529/90-12 & 50-530/90-12.Corrective Action: Wiring in PPS Cabinets & Cabinet Drawers Reworked in Accordance W/Approved Work Authorization Documents
IR 05000528/19900021990-06-19019 June 1990
Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite
ML17305A9041990-06-19019 June 1990
Describes Current Status & Provides Description of Actions Taken to Ensure Continued High Reliability of Emergency Lighting Sys,Per Insp Repts 50-528/90-02,50-529/90-02 & 50-530/90-02.Emergency Lights Mfg by Emergi-Lite
ML17305A8891990-06-15015 June 1990
Informs NRC That post-restart Items Due Prior to Scheduled Restart Have Been Completed on Schedule W/Listed Exceptions
ML17305A8871990-06-14014 June 1990
Advises That Fuel Pool Cooling & Cleanup Procedures Being Restructured,Per Response to Violations in Insp Repts 50-528/89-36 & 50-530/89-36
ML17305A8731990-06-0808 June 1990
Responds to Bulletin 88-005 Re Product Forms Other than Fittings & Flanges for Plant.Significant Number of Lugs Delivered to Plant.Util Should Be Notified,If NRC Previous Review of Records Has Identified Other Product Forms
ML17305A9421990-06-0101 June 1990
Forwards Pinnacle West Response to State of Az Corp Commission Complaint Filed W/Us Securities & Exchange Commission on 900521,to Revoke Exemption from Public Utils Holding Co Act
ML17305A8661990-05-31031 May 1990
Forwards Projected 1990 Cash Flow Statements
ML17305A8391990-05-31031 May 1990
Forwards 1990 Reactor Containment Bldg Integrated Leak Rate Test,Final Rept.
ML17305A8571990-05-31031 May 1990
Forwards Amended Pages of Feb,Mar & Apr 1990 Monthly Operating Repts for Palo Verde Nuclear Generating Station Unit 2
ML17305A8201990-05-23023 May 1990
Provides Status of Improvements to Eliminate Possibility of Multiple Control Element Assembly Drop Events.Licensee Developed Mod to Ground Fault Detection Sys to Assure Continuous Monitoring & Annunciation of Any Future Faults
ML20043B6421990-05-19019 May 1990
Forwards Amend 26 to Security Plan.Amend Withheld (Ref 10CFR2.790(d) & 10CFR73.21)
ML17305A7841990-05-15015 May 1990
Forwards Special Rept 2-SR-90-002 Re Steam Generator Tube Plugging Due to Inservice Insp Activities.Twenty Tubes Plugged in Steam Generator 1 & ninety-one Tubes Plugged in Steam Generator 2
ML17305A8721990-05-14014 May 1990
Forwards Arizona Corp Commission Complaint Filed W/Us Securities & Exchange Commission Seeking Revocation or Mod of Exemption of Pinnacle West Capital Corp.Complaint Wholly W/O Merit
ML17305A7621990-05-11011 May 1990
Responds to NRC 900413 Ltr Re Violations Noted in Insp Repts 50-528/90-03,50-529/90-03 & 50-530/90-03.Corrective Actions: Night Order Written for Guidance on Use of Instrumentation W/Maint Tag Present
ML17305A7921990-05-0808 May 1990
Forwards Public Version of Rev 2 to EPIP-14, Dose Assessment. W/900523 Release Memo
ML20043A0511990-05-0303 May 1990
Forwards Public Version of Revised Epips,Including Procedure Change Notice 11 to Rev 12 to EPIP-04 & Procedure Change Notice 1 to Rev 6 to EPIP-15
ML17305A7421990-05-0303 May 1990
Responds to 900330 Enforcement Conference Re Violations Noted in Insp Repts 50-528/90-04,50-529/90-13 & 50-530/90-13.Corrective Action:Special Locking Mechanisms Installed on Currently Posted Radiation Area Doors & Gates
ML17305A8861990-04-30030 April 1990
Forwards EPIP Update,Including Rev 7 to EPIP 02,Rev 12 to EPIP 03 & Rev 9 to EPIP 20.W/o Encl
ML17305A7381990-04-30030 April 1990
Forwards Annual Environ Operating Rept for 1989 & Annual Rept for Salt Deposition Monitoring Program 1989.
ML17305A7131990-04-20020 April 1990
Responds to NRC 900321 Ltr Re Violations Noted in Insp Rept 50-530/90-08.Corrective Action:Plant Guideline Providing Addl Guidance Re Prioritization of Work Promulgated
ML17305A6891990-04-16016 April 1990
Forwards Rev to Cycle 3 Reload Analysis Rept,Submitted 891024.Rev Reflects Early end-of-cycle Unit Shutdown & Replacement of Eight New Fuel Assemblies
ML17305A7011990-04-12012 April 1990
Forwards Rev 3 to Palo Verde Nuclear Generating Station Post-Restart Actions, Per JB Martin 891224 Ltr
ML17305A7081990-04-0909 April 1990
Forwards post-exam Security Agreements for Dk Hendrick, D Ensign,M Alavi & Author.Agreement Certifies That Signatories Will Not Divulge Info Re 900320 Exams
1990-09-17
[Table view] |
Text
REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)
ACCESSION "NBR:801 0010207 DOCRDATE: 84/09/27 NOTARIZED;; NQ DOCKET FACILiSTN~50~528 "Palo Verde Nuclear StatianR Unit li Ar)zona, Publi 05000528
'STN 50 529 Palo Verde, Nuclear Stations Unit 2i Ar izona Publi'5000529 STN~50 530 Palo Verde Nuclear Stationi Unit 3g Arizona Publi 05000530 AUTH INANE; AUTHHDR AFFILIATION VAN,BRUNTgE',K~ Arizona Public Service -Co ~
RKC I P ~ NAME. RECIPIENT AFFILIATION KNIGHTlONiG I Licensing Branch <<3 SUBJKCTj 'Confirms info discussed, at 840911 meeting w/Licitra -L Kubicki in,Bethesda<MD re'evised fire protection evaluation rept'ncluded -in Amend 13,to FSAR.FSAR will be amended to address"issue re fire dampers, DISTRIBUTION CODE: .BOOED COPIES RECEIVEDgl.,TR J. ENCL P SIZE: 'i'.
.TITLKt Licensing Submittal: Fire Protection NOTES)Standardized plant, 05000528 Standardized plant ~ 05000529
'Standardized plantB 05000530 RECIPIENT'D COPIES REC IP IENT 'COPIES GOOK/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB3 BC LICITRArE 01 INTERNAL'DM/LFMB 1 ELD/HDS3 1 IK FII El 07 06 NRR/DSI/ASB EG F K. 0$ 1 RGN5 1 EXTERNAL'! AGRS 10: LPDR- 03
,NRC; PDR 02" NSIG 05 NTIS TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL:
T f 4 f,'4 T>> 4> ~ I
,>>'I) 'P C>h> f 4 K >(y>> 4 4 >II l"" 4'4 wc r 4'>Q<<4 >r
~ r I, i g >>' '
w ll << '
>>, <<) 'hh f '4 W,ll rl ll l I'I lrrl '/
'1 w ll'l 4 <<" 4 I '
g (
i,lff >r '> I<<<< 4<<>><< >>>hf rr" fI wf 4, rlr'fl,rr > r,l>>>f f '> ll I'4" w'h I I,
~T I. w I<<T E Tf' f p,f
<< I(hr f 0 l<<" l 4> 4 e'I" f 4 If jl jf w>> I >> il f 4.4 r>> 44 f.f r% f'll I<<
T fl
><<fT f I
~ h
>> << j lyly@ 4J
> fJ > <<rr<<rg f lip 4<<
4
Arizona Public-Service Company P.O. BOX 21666 ~ PHOENIX, ARIZONA 65036 ANPP-30680-EEVBJr/TFg/DKN September 27, 1984 Director of Nuclear Reactor Regulation Attention: Mr. George Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Fire Protection Evaluation Docket Nos. STN-50-528/529/530 File: 84-056-026'.1.01.10
Dear Mr. Knighton:
This will confirm information discussed with Messrs. Licitra and Kubicki at a meeting held in Bethesda, MD, on September ll, 1984 on an item in the revised Fire Protection Evaluation Report included in FSAR Amendment 13.
FSAR Question 9A.68, item b, and this letter pertain to Fire Dampers. Our response to FSAR Question 9A.68 indicates that, where the damper is mounted on the surface of the wall, the structural steel attaching the damper to the wall and the first duct support will be coated with fire retardant material of a rating equal to that of the wall.
Upon further investigation, it has been found that this specific type of installation occurs only in a few areas with little or no combustible loading, such as HVAC shafts, essential chiller room, corridors or in rooms where automatic fire suppression systems are installed to limit fire severity.
Following is a fire protection evaluation of the areas where surface mounted dampers are installed:
- 1. Control Building
- a. Dampers installed on the interior wall of the HVAC shafts (2 hr shaft w/l-l/2 hr dampers) are exposed to no combustible load.
8409i7 salao>0207 0500052S pcP PDR ADOCK PDR F
Q,<V. i> KA,:
ANPP-30680 Page 2.
- b. Dampers installed on the exterior wall of the HVAC shafts
- are in fire zones with detection and automatic suppression systems (C02 or water). This would, mitigate the effects of fire and limit the heat exposure. The duct supports are seismically designed and therefore are of substantial steel construction. They would withstand a design basis fire with automatic suppression.
- c. There is one surface mounted damper at the 74'evel (essential chiller room) of the Control Building in the 3 hr rated central wall. The equivalent fire severity in this fire zone (No. 1) is less than 15 minutes consisting primarily of charcoal filters located about 40 feet away.
Smoke detection is installed in the room for early warning.
This installation provides reasonable assurance that a fire will not propagate through the wall. On the other side of the damper is a two hour rated concrete soffit containing no combustibles. There is no direct communication with the adjacent fire area.
- 2. Auxiliary Building
- a. Zone 37A corridor, 70 foot level. There is one surface mounted damper in a one hour rated portion of a concrete wall. The fire loading is less than 20 minutes and there is smoke detection installed in the zone for early warning.
Spatial separation on either side of the wall between redundant safe shutdown equipment is approximately 60 feet total, with no intervening combustibles. This installation provides adequate separation and protection of safe shutdown equipment.
- b. Zone 52A corridor, 120 foot level. There is one surface mounted damper in a one hour rated portion of a concrete wall. The combustible loading consists of cable trays (69 minutes) but is protected by an automatic detection and water suppression system. Redundant safe shutdown equipment is also separated by approximately 80 feet to that located in zone 52B. This installation provides adequate separation and protection of safe shutdown equipment.
0 I f
J
ANPP-30680 Page 3.
Based upon the above analysis of fire hazards, equipment separation and fire suppression systems available, the surface mounted dampers in these areas will provide adequate protection without additional fire proofing. The FSAR will be revised in a future amendment.
Very truly yours, E. E. Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVBJr/TFQ/DKN/dh cc: E. A. Licitra D. J. Kubicki A. C. Gehr
tl 1i
ANPP-30680 Page 4.
bcc's:
E. E. Van Brunt, Jr.
A. C. Rogers W. F. Quinn W. E. Ide T. F. Quan G. J. Volk J. R. Bynum J. D. Houchen W. F. Fernow R. W. Meyer L. G. Papworth L. Harris K. W. Gross W. G. Bingham (B)
J. R. Schuh (B)
K. Ng (B)
N. E. Baldasari (B)
J. Curry (B)
L. Barbe (B)
-t~
1
/
p ll
