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| | issue date = 05/09/1988 | | | issue date = 05/09/1988 |
| | title = Provides Confirmation That Required Procedures Re Generic Ltr 88-03 Concerning Generic Issue 93, Steam Binding of Auxiliary Feedwater Pumps, in Place & Will Be Maintained | | | title = Provides Confirmation That Required Procedures Re Generic Ltr 88-03 Concerning Generic Issue 93, Steam Binding of Auxiliary Feedwater Pumps, in Place & Will Be Maintained |
| | author name = KUEMIN J L | | | author name = Kuemin J |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:. I, -* consumers Power l'OWERINli NllCHlliAN'S l'ROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 May 9, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -STEAM BINDING OF AUXILIARY FEEDWATER PUMPS -RESPONSE TO GENERIC LETTER 88-03 Generic Letter 88-03 concerning the resolution of Generic Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" required Licensees to confirm that certain procedures are in place and will be maintained. | | {{#Wiki_filter:.I, consumers Power l'OWERINli NllCHlliAN'S l'ROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 May 9, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - |
| In particular, it that the Licensee should: J. Maintain procedures to monitor fluid conditions within the AFW system each shift during times when the system is required to be operable. | | STEAM BINDING OF AUXILIARY FEEDWATER PUMPS - RESPONSE TO GENERIC LETTER 88-03 Generic Letter 88-03 concerning the resolution of Generic Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" required Licensees to confirm that certain procedures are in place and will be maintained. In particular, it r~quired that the Licensee should: |
| This monitoring should ensure that fluid temperature at the AFW pump discharge is maintained at about ambient levels. 2. Maintain procedures for recognizing steam binding and for restoring the AFW system to operable status, should steam binding occur. As stated in our response to IE Bulletin 85-01 dated February 26, 1986, the requirement to monitor the Auxiliary Feedwater piping is a part of our Auxiliary Building Data Sheet (Primary). | | J. Maintain procedures to monitor fluid conditions within the AFW system each shift during times when the system is required to be operable. This monitoring should ensure that fluid temperature at the AFW pump discharge is maintained at about ambient levels. |
| This data sheet is completed by the Auxiliary Operator each shift and is reviewed and initialed by the shift Supervisor. | | : 2. Maintain procedures for recognizing steam binding and for restoring the AFW system to operable status, should steam binding occur. |
| In addition, Attachment 2, Part III (system testing) to the Feedwater System Operating Procedure (SOP 12) specifies testing for check valve back leakage. This part includes guidelines for restoring the AFW system should high pump temperatures occur. By this letter, Consumers Power Company provides confirmation that the required procedures are in place and will be maintained. | | As stated in our response to IE Bulletin 85-01 dated February 26, 1986, the requirement to monitor the Auxiliary Feedwater piping is a part of our Auxiliary Building Data Sheet (Primary). This data sheet is completed by the Auxiliary Operator each shift and is reviewed and initialed by the shift Supervisor. |
| OC0488-0116-NL02 8805120272 8:30509 PDR ADOCK 05000255 P DCD I'\ , Steam Binding of Auxiliary Feedwater Pumps -Response to Generic Letter 88-03 May 9, 1988 3 A copy of the current data sheet and the pertinent page for SOP 12 *is attached. L Kuemin Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector | | In addition, Attachment 2, Part III (system testing) to the Feedwater System Operating Procedure (SOP 12) specifies testing for check valve back leakage. |
| -Palisades Attachment OC0488-0116-NL02 CONSUMERS POWER COMPANY Palisades Plant Docket 50-255 License DPR-20 Response to Generic Letter No 88-03 Dated February 17, 1988 At the request of the Commission and pursuant to the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits our response to NRC letter dated February 17, 1988, entitled,"Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps (Generic Letter 88-03)." Consumers Power Company's response is dated May 9, 1988. CONSUMERS POWER COMPANY David P Hoffman, Nuclear Operations Sworn and subscribed to before me this 9th day of May 1988. E Buehrer No ary Public Jackson County, Michigan My commission expires October 31, 1989 OA0488-0116-NL02 | | This part includes guidelines for restoring the AFW system should high pump temperatures occur. |
| .: .. ''' .,, OPERATOR'S INI flALS 11*10 Hill EQUIPMENT ROOM F-54A PURIFICATION FILTER AP dPl-0204 (< 15 P51) F-54B PURIFICATION Fil TER AP dPl-0205 (< 15 PSll WGDT T-101APRESSURE PIA-1160 (< 100 PS1G) WGDT T-101B PRESSURE .PIA-1161 | | By this letter, Consumers Power Company provides confirmation that the required procedures are in place and will be maintained. |
| (< 100 PSIG) WGDT T-101C PRESSURE PIA-1162 (< 100 P51G) WEST SAFEGUARDS SUMP'ROOM LEI/EL ll-10078 (2-15%) EAST SAFEGUARDS SUMP1ROOM LEllEL Ll-11108 (2* | | OC0488-0116-NL02 8805120272 8:30509 PDR ADOCK 05000255 P DCD |
| C-33 PANEL SECURE (2 LOCIC.S) WASTE GAS SURGE TANI( PRESSURE PIA-1111 (14* 1 5 PSIA) WGDT T*68A PRESSURE PIA-1119 (< 100 PSIG) WGDT T-68B PRESSURE PIA-1120 (< 100 PS1Gl WGDT T-68C PRESSURE PIA-1121 (< 100 PSIG) WASTE GAS DECAY TANK IN SERll1CE SOUTH LAUNDRY DRAIN TANK LEVEL LIA*l 124 (20*
| | |
| NORTH LAUNDRY DRAIN TANK LE\/El LIA-1127 (20*7S%) WEST DIRTY WASTE TANK LEVEL LIA-1115 (20-92%) EAST DIRTY WASTE TANK LEVEL LIA* 1117 {20-92.,.l NORTH FILTERED WASTE TANK LEVEL LIA* 11 30 -(0-88'+-ii)
| | I'\ |
| SOUTH Fil TE RED WAS TE TANK LEVEL LIA* 1133 Fil TERED WASTE TANK IN SERlll(E PRIMARY SYSTEM DRAIN TANK PRESSURE PIA-100'1 (0-S PS1G) PRIMARY SYSTEM DRAIN TANI( LEI/El LIA-1001 VACUUM DEGAS1F1ER TANK LEI/EL LI(* 1061 (40-60%) VACUUM DE GA SI FIE RT ANI( PRESSURE Pl-1004 (3*10PSIA)
| | Steam Binding of Auxiliary Feedwater Pumps - 3 Response to Generic Letter 88-03 May 9, 1988 A copy of the current data sheet and the pertinent page for SOP 12 *is attached. |
| VACUUM DEGAS1F1EA PUMP DISCH Pl* 1005 (65*90 PSIG) CLEAN WASTE ACVR TANI< PRESSURE PIA-1065 (<lPSIG) 'A' CLEAN WASTE AC\/A TANK LEVEL llA-1012 (<95"'i.l
| | /.~ |
| 'B' CLEAN WASTE ACllA TANK LEVEL LIA-1014
| | L Kuemin Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment OC0488-0116-NL02 |
| *c CLE AN WAS TE AC11A T ANIC LEVEL LIA-1016 | | |
| 'D' CLEAN WASTE. RCVA TANK LEllEL LIA-1018 (<95%) CLEAN WASTE ACVA TANK IN SERVICE NORTH CHEM DRAIN TANK LEVEL LIA-1006 SOUTH CHEM DRAIN TANK LEVEL LIA-1007 (20-80,.)
| | CONSUMERS POWER COMPANY Palisades Plant Docket 50-255 License DPR-20 Response to Generic Letter No 88-03 Dated February 17, 1988 At the request of the Commission and pursuant to the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits our response to NRC letter dated February 17, 1988, entitled,"Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps (Generic Letter 88-03)." |
| FUEL POOL DEMIN :. p dPIA 0924 (< 30 PSI) CONSUMERS POWER COMPANY .ILIARY BUILDING DATA SHEET e (Primary) | | Consumers Power Company's response is dated May 9, 1988. |
| A B c DRAIN TANK LEI/EL LI *1008 (20 NORTH TREATED WASTE TANK LEI/EL (. ... LIA*1046 (0-90%) SOUTH TREATED WASTE TANIC LEI/EL LIA* 1048 1ND1CATED DILUTION FLOW FR-1050 C-161 GAS BOTTLES (3) (>200 PSIG) STATION 5 BOTTLE PRESSURE Pl-22 79A ( 2000 PSIG) STATIONS HEADER PRESSURE Pl-2279B (80-90 PSIG) 'A' CCW HEAT EXC11 dPl-0918 (< 1 7 PSI) 'B' CCW HEAT EXCH 6P dPl-0919 (< 17 PSI) y T .....-T .,,. 1J *c* AFW DISCH PIPING TO B SIG CCW TtMPtlUlTV"E TIC-OB21 (74-90° f) r . "( ... _y) A&B AFW PIPING TO B SIG l A&B AFW PIPING TO A S1G I \ 'C' AFW PIPING TO A StG . --STATI'QN 1 BOTTLE PJftSSURE P1-2273A ( 2000 PSIG) STATION 1 HEADER PRESSURE Pl-2 2 738 (60* 70 PSIG) ST A TION 1 A BOTTLE PRE SS URE Pl-2280A ( 2000 PSIG) STATION lA HEADER PRESSURE P1*2280B (80*90 PSIGl SIRW TANK RECIRC TEMPERATURE n-0371 <45-100* Fl SPENT FUEL POOL PUMPIHX ROOM TREATED WASTE EQUIPMENT ROOM '8' BORIC ACID STOR TANK TEMPERATURE TIC-0206 (158-16S°Fl
| | CONSUMERS POWER COMPANY David P Hoffman, Nuclear Operations Sworn and subscribed to before me this 9th day of May 1988. |
| 'B' BORIC ACID STOA TANK TEMPERATURE TIC-0207 (lSB-165° F) 'A' BORIC ACID STOA TANK TEMPERATURE TIC-0208 {158-165* | | E Buehrer No ary Public Jackson County, Michigan My commission expires October 31, 1989 OA0488-0116-NL02 |
| Fl 'A' BORIC ACID STOA TANIC: TEMPERATURE TIC-0209 (158*165° F) PURIFICATION DE MIN dPl-0203 (< 15 PSI) C* 162 GAS BOTTLES (3) ( >200 PS1Gl PUMP ROOM 'A' CHARGING PUMP OIL PRESSURE Pl-0217A (> 20 PSIG) *9* CHARGING PUMP OIL PRESSURE Pl-021 78 (>20 PSIG} 'C Ct1AAGING PUMP OIL PRESSURE I Pl-02 17( ( > 20 PSIG) 'A' CHARGING PUMP SEAL LEAKAGE ( < 500 ML/MIN) 'B' CHARGING PUMP SEAL LEAKAGE '. ( < 200 ML/MIN) *c* CHARGING PUMP SEAL LEAKAGE (<200 ML'MIN) PRIMARY SYSTEM DRAIN TANK PUMP ROOM S112W TAN< i.JOZ. Z.1.£
| | |
| .. *PIPING SHOULD BE COOL TO TOUCH. SIGNIFYING NO BA.CK LEAKAGE FROM THE STEAM GENERATORS I I 8 I A B c ! ' I I **.** .,. ... *:-: .. < . :T.r ' i l I ! I I ! I ! . * .. " .. I ' ! ' I ! --r-.. -----j ! ' '
| | CONSUMERS POWER COMPANY |
| I I ! I I l ! I i I ! I !
| | .ILIARY BUILDING DATA SHEET (Primary) e A B c A B c E~UIPMENT DRAIN TANK LEI/EL OPERATOR'S INI flALS LI *1008 (20 90~.) |
| WG COMPRESSOR ROOM LAUNDRY TANK ROOM C-54 WG COMPRESSOR ROOM BAMIX TANK STATUS BA EYE WASH STATION FLUSH AUX BUILDING CHILLER & HN ROOM FUEL POOL TEMPERATURE TIA-0925 FUEL POOL LEVEL LOCAL VISUAL SFP GATE N 2 PRESSURE Pl 2252 (80-110°F)
| | ~* :~ NORTH TREATED WASTE TANK LEI/EL 11*10 Hill EQUIPMENT ROOM (. ... LIA*1046 (0-90%) ! |
| {2*8" <SKIM) { 10PS1G) SFP AREA SAFETY CHAINS IN PLACE SFP VENT & MCC ROOM V-8A&B VENT EQUIPMENT ROOM CV-3029 HP AIR Pl-30298 CV-3029 LP AIR Pl-3029A CV-3057 HP AIR Pt-30578 CV-3057 LP AIR Pl-3057A EAST SAFEGUARD HP AIR Pl-0439 * {170-175PSIG) | | F-54A PURIFICATION FILTER AP SOUTH TREATED WASTE TANIC LEI/EL ' |
| (55-65 PS1G) { 170-1 75 PSIG) (55-65 PSIG) (300-325 PSIG) A B c CV-3031 HP AIR Pl-30318 CV-3031 LP AIR P1-J031A CV-3030 HP AIR Pl-30308 CV-3030 LP AIR Pl-3030A WEST SAFEGUARD HP AIR Pt-0441 ( 170-1 75 PSIG) (55-65 PS1G) ( 1 70-1 75 PSIG) (55-65 PSIG) (300-325 PSIG) CONTAINMENT SAFETY CHAINS CONTAINMENT TOUR IF REACTOR HEAD REMOVED* CHECK FOR LOOSE MA TE RIAL SUPERVISOR"S REVIEW COMMENTS A NOTE: Out-of-specification readings are to be circled in red ink, and a brief explanation concerning the problem provided in the Comments Section.
| | dPl-0204 (< 15 P51) LIA* 1048 (0*90~o) |
| SYSTEM TESTING ?roe No SOP 12 Attachment 2 Revision 12 Page 2 of 2 3. Stop the **K-7A; **K-78 auxiliary oil pump by turning its Local hand switch (Panel '"'''EC-24;
| | F-54B PURIFICATION Fil TER AP 1ND1CATED DILUTION FLOW I dPl-0205 (< 15 PSll FR-1050 I WGDT T-101APRESSURE C-161 GAS BOTTLES (3) **.** .,.... *:-: :~ |
| ''*EC-25) from "auto" to "off" to "auto." III. TEST FOR CHECKVALVE BACKLEAKAGE
| | PIA-1160 (< 100 PS1G) (>200 PSIG) .. < . |
| : l. Verify, by carefully touching the AFW piping near each flow control valve, that there is no backleakage from the steam generators. (If the piping is cool to the touch, significant backleakage does not exist.)
| | WGDT T-101B PRESSURE STATION 5 BOTTLE PRESSURE |
| * 2. If the AFW piping is hot to the couch, take the following actions: 2.1 Notify Control Operator and Shift Supervisor. | | .PIA-1161 (< 100 PSIG) Pl-22 79A ( ~ 2000 PSIG) |
| 2.2 Check temperature of the associated AFW pump(s). 2.3 Start an AFW pump and flush the hot portions of the AFW piping to the steam generator(s).
| | WGDT T-101C PRESSURE STATIONS HEADER PRESSURE :T.r PIA-1162 (< 100 P51G) Pl-2279B (80-90 PSIG) |
| 2.4 Monitor piping and pump temperatures for reoccurrence of backleakage.
| | WEST SAFEGUARDS SUMP'ROOM LEI/EL 'A' CCW HEAT EXC11 ~p ll-10078 (2-15%) dPl-0918 (< 17 PSI) |
| 2.S If an AFW pump is found too hot to touch (Step 2.2) or if high piping temperatures reoccur a Work Request/Work Order, to repair the leaking valves at the next shutdown, should be issued.
| | EAST SAFEGUARDS SUMP1ROOM LEllEL 'B' CCW HEAT EXCH 6P Ll-11108 (2* 15~*l dPl-0919 (< 17 PSI) i C-33 PANEL SECURE (2 LOCIC.S) y T . .- |
| * 2.6 If backleakage is sufficient to cause high pump temperatures, isolation of the leakage path with one of the FOGG valves should be considered. (Backleakage has actually disabled AFW pumps by steam-binding at other nuclear plants.) With the backleakage path isolated, the pump and local discharge piping should be vented to refill the pump with cool condensate.
| | ~ *c* AFW DISCH PIPING TO B SIG T .,,. 1J l I |
| The discharge piping should then be flushed to the steam generators and the FOGG valve reopened.
| | WASTE GAS SURGE TANI( PRESSURE PIA-1111 (14* 15 PSIA) |
| NOTE: Isolating FOGG valve renders associated flow control valve inoperable and initiates a 72 hrs LCO; see Technical Specification 3.S. pa0280-l043c-89-91}}
| | CCW TtMPtlUlTV"E TIC-OB21 (74-90° f) ! |
| | r . "( . . _y) |
| | WGDT T*68A PRESSURE PIA-1119 (< 100 PSIG) A&B AFW PIPING TO B SIG I WGDT T-68B PRESSURE PIA-1120 l A&B AFW PIPING TO A S1G I |
| | (< 100 PS1Gl WGDT T-68C PRESSURE PIA-1121 WASTE GAS DECAY TANK IN SERll1CE |
| | (< 100 PSIG) I \ . - |
| | 'C' AFW PIPING TO A StG STATI'QN 1 BOTTLE PJftSSURE I |
| | P1-2273A ( ~ 2000 PSIG) |
| | SOUTH LAUNDRY DRAIN TANK LEVEL STATION 1 HEADER PRESSURE LIA*l 124 (20* 75~o) Pl-2 2 738 (60* 70 PSIG) |
| | NORTH LAUNDRY DRAIN TANK LE\/El ST ATION 1A BOTTLE PRE SS URE LIA-1127 (20*7S%) Pl-2280A ( ~ 2000 PSIG) |
| | WEST DIRTY WASTE TANK LEVEL STATION lA HEADER PRESSURE LIA-1115 (20-92%) P1*2280B (80*90 PSIGl EAST DIRTY WASTE TANK LEVEL SIRW TANK RECIRC TEMPERATURE LIA* 1117 {20-92.,.l n-0371 <45- 100* Fl NORTH FILTERED WASTE TANK LEVEL SPENT FUEL POOL PUMPIHX ROOM LIA* 11 30 -(0-88'+-ii) |
| | SOUTH Fil TE RED WAS TE TANK LEVEL LIA* 1133 (0-88~) TREATED WASTE EQUIPMENT ROOM I Fil TERED WASTE TANK IN SERlll(E '8' BORIC ACID STOR TANK TEMPERATURE TIC-0206 (158-16S°Fl PRIMARY SYSTEM DRAIN TANK PRESSURE 'B' BORIC ACID STOA TANK TEMPERATURE PIA-100'1 (0-S PS1G) TIC-0207 (lSB-165° F) ' |
| | PRIMARY SYSTEM DRAIN TANI( LEI/El LIA-1001 (20-90~*.) |
| | 'A' BORIC ACID STOA TANK TEMPERATURE TIC-0208 {158-165* Fl VACUUM DEGAS1F1ER TANK LEI/EL LI(* 1061 (40-60%) |
| | 'A' BORIC ACID STOA TANIC: TEMPERATURE TIC-0209 (158*165° F) I |
| | --r-..-----j VACUUM DE GA SI FIE RT ANI( PRESSURE PURIFICATION DE MIN ~p ! |
| | Pl-1004 (3*10PSIA) dPl-0203 (< 15 PSI) '' |
| | VACUUM DEGAS1F1EA PUMP DISCH Pl* 1005 (65*90 PSIG) |
| | C* 162 GAS BOTTLES (3) |
| | ( >200 PS1Gl H~i~ +;;;,?;w~ |
| | CLEAN WASTE ACVR TANI< PRESSURE PIA-1065 (<lPSIG) CWRT~ESIN PUMP ROOM I |
| | 'A' CLEAN WASTE AC\/A TANK LEVEL 'A' CHARGING PUMP OIL PRESSURE I llA-1012 (<95"'i.l Pl-0217A (> 20 PSIG) |
| | 'B' CLEAN WASTE ACllA TANK LEVEL *9* CHARGING PUMP OIL PRESSURE !I LIA-1014 (<95~**> Pl-021 78 (>20 PSIG} I |
| | *c CLE AN WAS TE AC11A TANIC LEVEL 'C Ct1AAGING PUMP OIL PRESSURE LIA-1016 (<95~.) I Pl-02 17( ( > 20 PSIG) |
| | 'D' CLEAN WASTE. RCVA TANK LEllEL LIA-1018 (<95%) |
| | 'A' CHARGING PUMP SEAL LEAKAGE |
| | ( < 500 ML/MIN) l CLEAN WASTE ACVA TANK IN SERVICE '. |
| | 'B' CHARGING PUMP SEAL LEAKAGE |
| | ( < 200 ML/MIN) |
| | ! I i |
| | NORTH CHEM DRAIN TANK LEVEL *c* CHARGING PUMP SEAL LEAKAGE I LIA-1006 (20*80~**) (<200 ML'MIN) |
| | SOUTH CHEM DRAIN TANK LEVEL LIA-1007 (20-80,.) PRIMARY SYSTEM DRAIN TANK PUMP ROOM I ! |
| | FUEL POOL DEMIN :. p dPIA 0924 (< 30 PSI) |
| | S112W TAN< i.JOZ. Z.1.£ 1..~ICA<.~ |
| | .. ~" |
| | *PIPING SHOULD BE COOL TO TOUCH. SIGNIFYING NO BA.CK LEAKAGE FROM THE STEAM GENERATORS |
| | ~,., II 8I |
| | |
| | A B c A CV-3031 HP AIR WG COMPRESSOR ROOM Pl-30318 ( 170-1 75 PSIG) |
| | CV-3031 LP AIR LAUNDRY TANK ROOM P1-J031A (55-65 PS1G) |
| | CV-3030 HP AIR C-54 WG COMPRESSOR ROOM Pl-30308 ( 170-1 75 PSIG) |
| | CV-3030 LP AIR BAMIX TANK STATUS Pl-3030A (55-65 PSIG) |
| | WEST SAFEGUARD HP AIR BA EYE WASH STATION FLUSH Pt-0441 (300-325 PSIG) |
| | AUX BUILDING CHILLER & HN ROOM FUEL POOL TEMPERATURE CONTAINMENT SAFETY CHAINS TIA-0925 (80-110°F) |
| | FUEL POOL LEVEL CONTAINMENT TOUR LOCAL VISUAL {2*8" <SKIM) |
| | SFP GATE N 2 PRESSURE IF REACTOR HEAD REMOVED* |
| | Pl 2252 { ~ 10PS1G) |
| | SFP AREA SAFETY CHAINS IN PLACE CHECK FOR LOOSE MA TE RIAL SFP VENT & MCC ROOM V-8A&B VENT EQUIPMENT ROOM CV-3029 HP AIR Pl-30298 * {170-175PSIG) |
| | CV-3029 LP AIR Pl-3029A (55-65 PS1G) |
| | CV-3057 HP AIR Pt-30578 { 170-1 75 PSIG) |
| | CV-3057 LP AIR Pl-3057A (55-65 PSIG) |
| | EAST SAFEGUARD HP AIR SUPERVISOR"S REVIEW Pl-0439 (300-325 PSIG) |
| | COMMENTS NOTE: Out-of-specification readings are to be circled in red ink, and a brief explanation concerning the problem provided in the Comments Section. |
| | |
| | ?roe No SOP 12 Attachment 2 Revision 12 Page 2 of 2 SYSTEM TESTING |
| | : 3. Stop the **K-7A; **K-78 auxiliary oil pump by turning its Local hand switch (Panel '"'''EC-24; ''*EC-25) from "auto" to "off" to "auto." |
| | III. TEST FOR CHECKVALVE BACKLEAKAGE |
| | : l. Verify, by carefully touching the AFW piping near each flow control valve, that there is no backleakage from the steam generators. (If the piping is cool to the touch, significant backleakage does not exist.) * |
| | : 2. If the AFW piping is hot to the couch, take the following actions: |
| | 2.1 Notify Control Operator and Shift Supervisor. |
| | 2.2 Check temperature of the associated AFW pump(s). |
| | 2.3 Start an AFW pump and flush the hot portions of the AFW piping to the steam generator(s). |
| | 2.4 Monitor piping and pump temperatures for reoccurrence of backleakage. |
| | 2.S If an AFW pump is found too hot to touch (Step 2.2) or if high piping temperatures reoccur a Work Request/Work Order, to repair the leaking valves at the next shutdown, should be issued. |
| | * 2.6 If backleakage is sufficient to cause high pump temperatures, isolation of the leakage path with one of the FOGG valves should be considered. (Backleakage has actually disabled AFW pumps by steam-binding at other nuclear plants.) With the backleakage path isolated, the pump and local discharge piping should be vented to refill the pump with cool condensate. The discharge piping should then be flushed to the steam generators and the FOGG valve reopened. |
| | NOTE: Isolating FOGG valve renders associated flow control valve inoperable and initiates a 72 hrs LCO; see Technical Specification 3.S. |
| | pa0280-l043c-89-91}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6871999-10-19019 October 1999
Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments
ML18066A6881999-10-19019 October 1999
Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments
ML18066A6741999-10-0202 October 1999
Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data
ML18066A6791999-10-0101 October 1999
Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants.
ML18066A6621999-09-30030 September 1999
Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS
ML18066A6601999-09-29029 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations.
ML18066A6471999-09-17017 September 1999
Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs
ML18066A6331999-09-0202 September 1999
Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant
ML18066A6261999-08-26026 August 1999
Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995
ML20211D5661999-08-17017 August 1999
Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc
ML18066A6111999-08-13013 August 1999
Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors
ML18066A5881999-07-30030 July 1999
Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS
ML18066A5921999-07-30030 July 1999
Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants.
ML18066A5971999-07-30030 July 1999
Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments
ML20210G8351999-07-29029 July 1999
Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR
ML18066A5651999-07-19019 July 1999
Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS
ML18066A5111999-06-29029 June 1999
Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl
ML20209B2081999-06-29029 June 1999
Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901
ML20210G8791999-06-23023 June 1999
FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant
ML18066A5061999-06-17017 June 1999
Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl
ML18066A4991999-06-11011 June 1999
Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided
IR 05000255/19970181999-06-0909 June 1999
Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev
ML18066A4921999-06-0909 June 1999
Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev
ML18068A6011999-06-0808 June 1999
Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation
ML18066A4881999-06-0404 June 1999
Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately
ML18066A4801999-05-24024 May 1999
Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513
ML18066A4721999-05-18018 May 1999
Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies
ML18066A4651999-05-17017 May 1999
Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl
ML18066A4611999-05-14014 May 1999
Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl
ML18068A5831999-05-0303 May 1999
Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432
ML20206J2411999-04-30030 April 1999
Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl
ML20217A8191999-04-29029 April 1999
Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam
ML20206E8271999-04-28028 April 1999
Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period
ML20207B4661999-04-23023 April 1999
Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified
ML18066A4531999-04-0707 April 1999
Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations
ML18066A4481999-04-0202 April 1999
Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program
ML18066A4471999-03-30030 March 1999
Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review
ML18066A4411999-03-30030 March 1999
Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review
ML18066A4441999-03-26026 March 1999
Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2
ML18066A4401999-03-25025 March 1999
Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested
ML18066A4191999-03-23023 March 1999
Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998
ML18066A4231999-03-22022 March 1999
Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl
ML20204F2091999-03-18018 March 1999
Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend
ML18066A4121999-03-18018 March 1999
Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled
ML18066A4141999-03-18018 March 1999
Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles
ML20204E5861999-03-16016 March 1999
Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants
ML18066A4131999-03-11011 March 1999
Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220
ML18068A5241999-02-12012 February 1999
Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii)
ML18068A5211999-02-11011 February 1999
Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML18066A6871999-10-19019 October 1999
Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments
ML18066A6881999-10-19019 October 1999
Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments
ML18066A6741999-10-0202 October 1999
Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data
ML18066A6791999-10-0101 October 1999
Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants.
ML18066A6621999-09-30030 September 1999
Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS
ML18066A6601999-09-29029 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations.
ML18066A6471999-09-17017 September 1999
Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs
ML18066A6331999-09-0202 September 1999
Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant
ML18066A6261999-08-26026 August 1999
Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995
ML20211D5661999-08-17017 August 1999
Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc
ML18066A6111999-08-13013 August 1999
Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors
ML18066A5971999-07-30030 July 1999
Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments
ML18066A5881999-07-30030 July 1999
Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS
ML18066A5921999-07-30030 July 1999
Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants.
ML18066A5651999-07-19019 July 1999
Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS
ML18066A5111999-06-29029 June 1999
Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl
ML20210G8791999-06-23023 June 1999
FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant
ML18066A5061999-06-17017 June 1999
Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl
ML18066A4991999-06-11011 June 1999
Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided
IR 05000255/19970181999-06-0909 June 1999
Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev
ML18066A4921999-06-0909 June 1999
Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev
ML18068A6011999-06-0808 June 1999
Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation
ML18066A4881999-06-0404 June 1999
Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately
ML18066A4801999-05-24024 May 1999
Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513
ML18066A4721999-05-18018 May 1999
Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies
ML18066A4651999-05-17017 May 1999
Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl
ML18066A4611999-05-14014 May 1999
Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl
ML18068A5831999-05-0303 May 1999
Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432
ML20206J2411999-04-30030 April 1999
Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl
ML20217A8191999-04-29029 April 1999
Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam
ML20206E8271999-04-28028 April 1999
Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period
ML20207B4661999-04-23023 April 1999
Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified
ML18066A4531999-04-0707 April 1999
Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations
ML18066A4481999-04-0202 April 1999
Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program
ML18066A4471999-03-30030 March 1999
Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review
ML18066A4411999-03-30030 March 1999
Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review
ML18066A4441999-03-26026 March 1999
Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2
ML18066A4401999-03-25025 March 1999
Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested
ML18066A4191999-03-23023 March 1999
Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998
ML18066A4231999-03-22022 March 1999
Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl
ML20204F2091999-03-18018 March 1999
Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend
ML18066A4141999-03-18018 March 1999
Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles
ML18066A4121999-03-18018 March 1999
Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled
ML20204E5861999-03-16016 March 1999
Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants
ML18066A4131999-03-11011 March 1999
Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220
ML18068A5241999-02-12012 February 1999
Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii)
ML18068A5211999-02-11011 February 1999
Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217
ML18066A4051999-02-10010 February 1999
Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46)
ML18066A3921999-01-29029 January 1999
Forwards Licensee Interpretation of TS Requirements for Performance of SRs as Applied to Instrumentation Channel Calibr.Ltr Established No New Commitments
ML18066A3891999-01-28028 January 1999
Submits Response to Concern Expressed in Insp Rept 50-255/98-06 Re Whether Palisades ISI Program Was Being Conducted IAW Applicable Requirements
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML18057A4811990-09-17017 September 1990
Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant
ML18057A4551990-09-0606 September 1990
Forwards Proprietary Info Re Dept of Labor Decision on Discharge of Former Employee of Util,Per NRC 900809 Request. No 10CFR50.7 Violation Occurred Since Job Performance Was Reason for Discharge.Encl Withheld (Ref 10CFR2.790(a)(6))
ML18057A4521990-09-0404 September 1990
Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated
IR 05000255/19900101990-09-0404 September 1990
Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated
ML18057A4371990-08-31031 August 1990
Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment
ML18057A4381990-08-31031 August 1990
Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place
ML20059E0001990-08-29029 August 1990
Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990
ML18057A4201990-08-24024 August 1990
Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting
ML18057A4021990-08-22022 August 1990
Forwards Missing Pages from Decommissioning Funding Rept, Consisting of Pages 25 & 26 of Attachment a to Exhibit E
ML18057A4241990-08-21021 August 1990
Forwards Application for Amend to License DPR-20,changing Tech Spec 4.5.1 Re Statement on Integrated Leak Rate Test
ML18057A4071990-08-21021 August 1990
Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable
ML18057A4121990-08-21021 August 1990
Forwards Application for Amend to License DPR-20,changing Tech Specs to Revise Wording for Reactor Protective Sys Trip Setting Limits for Steam Generator Low Water Level
ML18057A4181990-08-21021 August 1990
Forwards Description of Changes Being Made to Plant Site Emergency Plan & Emergency Plan Changes.Change Allows Reduction in Shift Staffing During Cold Shutdown for Stated Staff
ML18057A3911990-08-17017 August 1990
Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program.
ML18057A3851990-08-17017 August 1990
Forwards Addl Info in Support of NRC Development of SER for full-term OL for Plant,Including Date of SER Providing Provisional OL to Plant & Summary of Valid Exemptions from 10CFR Regulations,Per Telcon
ML18057A3841990-08-17017 August 1990
Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr
ML18057A3821990-08-14014 August 1990
Requests That Bechtel-KWU Rept 128901/MJS, Full Flow Testing of Motor-Operated Valve MO-1042A, Be Withheld (Ref 10CFR2.790(b)(1))
ML18057A3721990-08-0808 August 1990
Forwards Addl Info Re Util Request for Exemption from Separation Criteria of 10CFR50,App R,Section III.G.2 Re Containment Air Room
ML20055J1421990-07-26026 July 1990
Responds to Commitment Oversight Issue Resulting from Insp Rept 50-255/90-08.Commitment Mgt Seminar Training Will Be Complete Prior to 901001
ML18057A3561990-07-26026 July 1990
Forwards Certification of Financial Assurance for Decommissioning
ML18057A3411990-07-18018 July 1990
Forwards Revised Proposed Tech Spec Page 6-3,now Designated as Page 6-1b,adding Section 6.3.4,now Designated as Section 6.3.5 to Remove Organization Charts,Per Generic Ltr 88-06
ML18057A3381990-07-16016 July 1990
Advises That Util Does Not Foresee Need to Rely on Section V.C of App G to Remain in Compliance W/Upper Shelf Energy (Use) Requirements Re Use of Matl in Reactor Beltline
ML18057A3281990-07-13013 July 1990
Responds to Request for Addl Info Re Second 10-yr Interval Insp Program,Per 900418 Telcon.Util 900329 Response Revised to Reflect That Certain Components in Class 2 Sys Should Not Be Exempted,Per IWC-1220 of 1974 ASME Code Section XI
ML18057A3191990-07-0909 July 1990
Forwards Performance Indicator Trend Graphs for Jan 1989 - May 1990
ML18057A3201990-07-0606 July 1990
Discusses Reassessment of Control Room Temp Following Station Blackout Event.Results of Analysis Indicate That Control Room Temp Will Remain Below 112 F for 4 H After Onset of Blackout
ML18057A3171990-07-0303 July 1990
Provides Summary of Upgrades Made to Plant Electrical Distribution Sys,Per 870714 Loss of Offsite Power Event When Inadvertent Actuation of Water Deluge Spray Sys for 1-2 Startup Transformer Resulted in Bus to Ground Fault
ML20058K3771990-07-0202 July 1990
Forwards Rev 26 to Security Plan.Rev Withheld (Ref 10CFR73.21(c))
ML18057A3111990-06-25025 June 1990
Forwards Endorsements 116 & 117 to Nelia Policy NF-179 & Endorsements 102 & 103 to Maelu Policy MF-50
ML18057A3101990-06-25025 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements on Corrective Actions.
ML18057A3031990-06-22022 June 1990
Provides Addl Info Re Environ Qualification of Instrument Circuit Associated W/Steam Generator Pressure Channel PT-0752D,per Insp Rept 50-255/90-05.Circuits Spliced Directly to Pigtail from Electrical Penetration Connector
ML18057A3001990-06-21021 June 1990
Concurs W/Nrc Change in Terminology & Submits Revised Proposed Section 4.14 of Tech Specs
ML18057A2771990-06-15015 June 1990
Forwards Corrected NRC Form 474 Re Simulation Facility Certification,Indicating Exceptions to Ansi/Ans 3.5
ML18057A2901990-06-13013 June 1990
Forwards Application for Amend to License DPR-20,revising Tech Spec 3.3.1.b Re Safety Injection Tank Min Level
ML18057A2941990-06-12012 June 1990
Advises That Submittal of Second Interval Inservice Insp Program Delayed from 900615 to 900715,per 900418 Telcon
ML18057A2711990-06-11011 June 1990
Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i in Order to Maintain Plant in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Request Based on 900608 Failure of Heater Transformer 15
ML18057A2641990-06-11011 June 1990
Provides Response to NRC Requalification Exam Rept Dtd 900410 on NRC Concerns Re Facility & Training Ctr Staffing. Adequate Staffing Will Be Maintained to Ensure Operator Requalification Program Successful
ML18057A2591990-06-11011 June 1990
Forwards Palisades Simulator Certification Submittal.
ML18057A2631990-06-10010 June 1990
Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i to Enable Plant to Be Maintained in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Waiver Requested for 900611-18
ML18057A2571990-06-0808 June 1990
Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-255/90-12.Corrective Actions:Continuing Training Program Will Be Developed for Supervisors That Will Discuss Fire Protection Program Implementation Topics
ML20043D0601990-06-0404 June 1990
Forwards Rev 25 to Security Plan,Including Changes to Security Plan Drawings to Clarify Protected Area Boundary within Plant Security Bldg & Vital Area Boundaries in Other Specific Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21)
ML18057A2581990-06-0101 June 1990
Forwards Revised Response to Violations Noted in Insp Rept 50-255/89-26.Concurs That Tests Performed Using Instrumented Insp Technique During 1988 Refueling Outage Considered Invalid
ML18057A2561990-05-31031 May 1990
Advises That No NPDES Notifications Required Nor Any Repts of Oil or Salt Occurred During Nov 1989 - Apr 1990
ML18057A2541990-05-30030 May 1990
Forwards Response to Technical Evaluation Rept EGG-NTA-8333 Which Evaluated Plant Compliance w/NUREG-0737,Item II.D.1 & Requested Addl Info Re New PORVs & Block Valves No Later than Jan 1990
ML18057A2511990-05-30030 May 1990
Forwards Final Response to Concerns Re Porv/Block Valve Mod, Per 900308 Meeting.Bechtel Technical Rept Withheld
ML18057A2501990-05-29029 May 1990
Forwards Investigation Rept Re Unsatisfactory Performance Testing of Fitness for Duty Program Blind Performance Test Samples
ML18057A2411990-05-24024 May 1990
Forwards Revised Application to Amend License DPR-20, Consisting of Revised Attachments 1 & 5 to 890227 Amend Request,Reflecting Transfer of Plant Ownership
ML18057A2311990-05-17017 May 1990
Forwards Analysis of Reactor Pressure Vessel Fast Neutron Fluence & PTS Ref Temps for Palisades Nuclear Plant. Rept Concludes That PTS Screening Criteria Will Be Exceeded at Axial Welds in Sept 2001 as Opposed to Mar 2002
ML18054B5861990-05-0707 May 1990
Forwards Monthly Trend Graph Rept for Jan 1989 - Mar 1990 Covering Safety Status Performance Indicators for HPSI, Auxiliary Feedwater,Emergency Ac Power,Lpsi,Containment Spray & Svc Water Sys
ML18054B5801990-04-30030 April 1990
Responds to Request for Addl Info on Proposed Administrative Changes to Tech Spec Section 3.0.4,per Generic Ltr 87-09. Licensee Will Implement Program to Assure Appropriate Level of Mgt Approval Required When Operating Conditions Changed
ML18054B5741990-04-25025 April 1990
Requests That Correspondence Re 890227 Application for Amend to License DPR-20 to Permit Transfer of Ownership of Plant Be Sent to Listed Address
1990-09-06
[Table view] |
Text
.I, consumers Power l'OWERINli NllCHlliAN'S l'ROliRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 May 9, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
STEAM BINDING OF AUXILIARY FEEDWATER PUMPS - RESPONSE TO GENERIC LETTER 88-03 Generic Letter 88-03 concerning the resolution of Generic Issue 93, "Steam Binding of Auxiliary Feedwater Pumps" required Licensees to confirm that certain procedures are in place and will be maintained. In particular, it r~quired that the Licensee should:
J. Maintain procedures to monitor fluid conditions within the AFW system each shift during times when the system is required to be operable. This monitoring should ensure that fluid temperature at the AFW pump discharge is maintained at about ambient levels.
- 2. Maintain procedures for recognizing steam binding and for restoring the AFW system to operable status, should steam binding occur.
As stated in our response to IE Bulletin 85-01 dated February 26, 1986, the requirement to monitor the Auxiliary Feedwater piping is a part of our Auxiliary Building Data Sheet (Primary). This data sheet is completed by the Auxiliary Operator each shift and is reviewed and initialed by the shift Supervisor.
In addition, Attachment 2, Part III (system testing) to the Feedwater System Operating Procedure (SOP 12) specifies testing for check valve back leakage.
This part includes guidelines for restoring the AFW system should high pump temperatures occur.
By this letter, Consumers Power Company provides confirmation that the required procedures are in place and will be maintained.
OC0488-0116-NL02 8805120272 8:30509 PDR ADOCK 05000255 P DCD
I'\
Steam Binding of Auxiliary Feedwater Pumps - 3 Response to Generic Letter 88-03 May 9, 1988 A copy of the current data sheet and the pertinent page for SOP 12 *is attached.
/.~
L Kuemin Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment OC0488-0116-NL02
CONSUMERS POWER COMPANY Palisades Plant Docket 50-255 License DPR-20 Response to Generic Letter No 88-03 Dated February 17, 1988 At the request of the Commission and pursuant to the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974, as amended, and the Commission's Rules and Regulations thereunder, Consumers Power Company submits our response to NRC letter dated February 17, 1988, entitled,"Resolution of Generic Safety Issue 93, "Steam Binding of Auxiliary Feedwater Pumps (Generic Letter 88-03)."
Consumers Power Company's response is dated May 9, 1988.
CONSUMERS POWER COMPANY David P Hoffman, Nuclear Operations Sworn and subscribed to before me this 9th day of May 1988.
E Buehrer No ary Public Jackson County, Michigan My commission expires October 31, 1989 OA0488-0116-NL02
CONSUMERS POWER COMPANY
.ILIARY BUILDING DATA SHEET (Primary) e A B c A B c E~UIPMENT DRAIN TANK LEI/EL OPERATOR'S INI flALS LI *1008 (20 90~.)
~* :~ NORTH TREATED WASTE TANK LEI/EL 11*10 Hill EQUIPMENT ROOM (. ... LIA*1046 (0-90%) !
F-54A PURIFICATION FILTER AP SOUTH TREATED WASTE TANIC LEI/EL '
dPl-0204 (< 15 P51) LIA* 1048 (0*90~o)
F-54B PURIFICATION Fil TER AP 1ND1CATED DILUTION FLOW I dPl-0205 (< 15 PSll FR-1050 I WGDT T-101APRESSURE C-161 GAS BOTTLES (3) **.** .,.... *:-: :~
PIA-1160 (< 100 PS1G) (>200 PSIG) .. < .
WGDT T-101B PRESSURE STATION 5 BOTTLE PRESSURE
.PIA-1161 (< 100 PSIG) Pl-22 79A ( ~ 2000 PSIG)
WGDT T-101C PRESSURE STATIONS HEADER PRESSURE :T.r PIA-1162 (< 100 P51G) Pl-2279B (80-90 PSIG)
WEST SAFEGUARDS SUMP'ROOM LEI/EL 'A' CCW HEAT EXC11 ~p ll-10078 (2-15%) dPl-0918 (< 17 PSI)
EAST SAFEGUARDS SUMP1ROOM LEllEL 'B' CCW HEAT EXCH 6P Ll-11108 (2* 15~*l dPl-0919 (< 17 PSI) i C-33 PANEL SECURE (2 LOCIC.S) y T . .-
~ *c* AFW DISCH PIPING TO B SIG T .,,. 1J l I
WASTE GAS SURGE TANI( PRESSURE PIA-1111 (14* 15 PSIA)
CCW TtMPtlUlTV"E TIC-OB21 (74-90° f) !
r . "( . . _y)
WGDT T*68A PRESSURE PIA-1119 (< 100 PSIG) A&B AFW PIPING TO B SIG I WGDT T-68B PRESSURE PIA-1120 l A&B AFW PIPING TO A S1G I
(< 100 PS1Gl WGDT T-68C PRESSURE PIA-1121 WASTE GAS DECAY TANK IN SERll1CE
(< 100 PSIG) I \ . -
'C' AFW PIPING TO A StG STATI'QN 1 BOTTLE PJftSSURE I
P1-2273A ( ~ 2000 PSIG)
SOUTH LAUNDRY DRAIN TANK LEVEL STATION 1 HEADER PRESSURE LIA*l 124 (20* 75~o) Pl-2 2 738 (60* 70 PSIG)
NORTH LAUNDRY DRAIN TANK LE\/El ST ATION 1A BOTTLE PRE SS URE LIA-1127 (20*7S%) Pl-2280A ( ~ 2000 PSIG)
WEST DIRTY WASTE TANK LEVEL STATION lA HEADER PRESSURE LIA-1115 (20-92%) P1*2280B (80*90 PSIGl EAST DIRTY WASTE TANK LEVEL SIRW TANK RECIRC TEMPERATURE LIA* 1117 {20-92.,.l n-0371 <45- 100* Fl NORTH FILTERED WASTE TANK LEVEL SPENT FUEL POOL PUMPIHX ROOM LIA* 11 30 -(0-88'+-ii)
SOUTH Fil TE RED WAS TE TANK LEVEL LIA* 1133 (0-88~) TREATED WASTE EQUIPMENT ROOM I Fil TERED WASTE TANK IN SERlll(E '8' BORIC ACID STOR TANK TEMPERATURE TIC-0206 (158-16S°Fl PRIMARY SYSTEM DRAIN TANK PRESSURE 'B' BORIC ACID STOA TANK TEMPERATURE PIA-100'1 (0-S PS1G) TIC-0207 (lSB-165° F) '
PRIMARY SYSTEM DRAIN TANI( LEI/El LIA-1001 (20-90~*.)
'A' BORIC ACID STOA TANK TEMPERATURE TIC-0208 {158-165* Fl VACUUM DEGAS1F1ER TANK LEI/EL LI(* 1061 (40-60%)
'A' BORIC ACID STOA TANIC: TEMPERATURE TIC-0209 (158*165° F) I
--r-..-----j VACUUM DE GA SI FIE RT ANI( PRESSURE PURIFICATION DE MIN ~p !
Pl-1004 (3*10PSIA) dPl-0203 (< 15 PSI)
VACUUM DEGAS1F1EA PUMP DISCH Pl* 1005 (65*90 PSIG)
C* 162 GAS BOTTLES (3)
( >200 PS1Gl H~i~ +;;;,?;w~
CLEAN WASTE ACVR TANI< PRESSURE PIA-1065 (<lPSIG) CWRT~ESIN PUMP ROOM I
'A' CLEAN WASTE AC\/A TANK LEVEL 'A' CHARGING PUMP OIL PRESSURE I llA-1012 (<95"'i.l Pl-0217A (> 20 PSIG)
'B' CLEAN WASTE ACllA TANK LEVEL *9* CHARGING PUMP OIL PRESSURE !I LIA-1014 (<95~**> Pl-021 78 (>20 PSIG} I
- c CLE AN WAS TE AC11A TANIC LEVEL 'C Ct1AAGING PUMP OIL PRESSURE LIA-1016 (<95~.) I Pl-02 17( ( > 20 PSIG)
'D' CLEAN WASTE. RCVA TANK LEllEL LIA-1018 (<95%)
'A' CHARGING PUMP SEAL LEAKAGE
( < 500 ML/MIN) l CLEAN WASTE ACVA TANK IN SERVICE '.
'B' CHARGING PUMP SEAL LEAKAGE
( < 200 ML/MIN)
! I i
NORTH CHEM DRAIN TANK LEVEL *c* CHARGING PUMP SEAL LEAKAGE I LIA-1006 (20*80~**) (<200 ML'MIN)
SOUTH CHEM DRAIN TANK LEVEL LIA-1007 (20-80,.) PRIMARY SYSTEM DRAIN TANK PUMP ROOM I !
FUEL POOL DEMIN :. p dPIA 0924 (< 30 PSI)
S112W TAN< i.JOZ. Z.1.£ 1..~ICA<.~
.. ~"
- PIPING SHOULD BE COOL TO TOUCH. SIGNIFYING NO BA.CK LEAKAGE FROM THE STEAM GENERATORS
~,., II 8I
A B c A CV-3031 HP AIR WG COMPRESSOR ROOM Pl-30318 ( 170-1 75 PSIG)
CV-3031 LP AIR LAUNDRY TANK ROOM P1-J031A (55-65 PS1G)
CV-3030 HP AIR C-54 WG COMPRESSOR ROOM Pl-30308 ( 170-1 75 PSIG)
CV-3030 LP AIR BAMIX TANK STATUS Pl-3030A (55-65 PSIG)
WEST SAFEGUARD HP AIR BA EYE WASH STATION FLUSH Pt-0441 (300-325 PSIG)
AUX BUILDING CHILLER & HN ROOM FUEL POOL TEMPERATURE CONTAINMENT SAFETY CHAINS TIA-0925 (80-110°F)
FUEL POOL LEVEL CONTAINMENT TOUR LOCAL VISUAL {2*8" <SKIM)
SFP GATE N 2 PRESSURE IF REACTOR HEAD REMOVED*
Pl 2252 { ~ 10PS1G)
SFP AREA SAFETY CHAINS IN PLACE CHECK FOR LOOSE MA TE RIAL SFP VENT & MCC ROOM V-8A&B VENT EQUIPMENT ROOM CV-3029 HP AIR Pl-30298 * {170-175PSIG)
CV-3029 LP AIR Pl-3029A (55-65 PS1G)
CV-3057 HP AIR Pt-30578 { 170-1 75 PSIG)
CV-3057 LP AIR Pl-3057A (55-65 PSIG)
EAST SAFEGUARD HP AIR SUPERVISOR"S REVIEW Pl-0439 (300-325 PSIG)
COMMENTS NOTE: Out-of-specification readings are to be circled in red ink, and a brief explanation concerning the problem provided in the Comments Section.
?roe No SOP 12 Attachment 2 Revision 12 Page 2 of 2 SYSTEM TESTING
- 3. Stop the **K-7A; **K-78 auxiliary oil pump by turning its Local hand switch (Panel '"'EC-24; *EC-25) from "auto" to "off" to "auto."
III. TEST FOR CHECKVALVE BACKLEAKAGE
- l. Verify, by carefully touching the AFW piping near each flow control valve, that there is no backleakage from the steam generators. (If the piping is cool to the touch, significant backleakage does not exist.) *
- 2. If the AFW piping is hot to the couch, take the following actions:
2.1 Notify Control Operator and Shift Supervisor.
2.2 Check temperature of the associated AFW pump(s).
2.3 Start an AFW pump and flush the hot portions of the AFW piping to the steam generator(s).
2.4 Monitor piping and pump temperatures for reoccurrence of backleakage.
2.S If an AFW pump is found too hot to touch (Step 2.2) or if high piping temperatures reoccur a Work Request/Work Order, to repair the leaking valves at the next shutdown, should be issued.
- 2.6 If backleakage is sufficient to cause high pump temperatures, isolation of the leakage path with one of the FOGG valves should be considered. (Backleakage has actually disabled AFW pumps by steam-binding at other nuclear plants.) With the backleakage path isolated, the pump and local discharge piping should be vented to refill the pump with cool condensate. The discharge piping should then be flushed to the steam generators and the FOGG valve reopened.
NOTE: Isolating FOGG valve renders associated flow control valve inoperable and initiates a 72 hrs LCO; see Technical Specification 3.S.
pa0280-l043c-89-91
