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{{#Wiki_filter:REGULATORY INFQR{'{ATION DISTR IBUTI QN SYSTEM (R IDS)ACCESSION NBR: S60627026S DQC.DATE: 86/06/23 NOTARIZED:
{{#Wiki_filter:REGULATORY INFQR{'{ATION DISTR IBUTIQN SYSTEM (R IDS)
YES FACIL: 50-220 Nine Ni le Point Nuclear Stations Unit ii Niagara Poue AUTH.NA{'{E AUTHOR AFFILIATION NANQAN, C.V.-Niagara Nohawk Power Corp.RECIP.NANE RECIPIENT AFFILIATION ZWOLINBKli J.A.BWR Pro Ject Directorate SUB JECT: Forwards Vals I Zc I I to Rev 4 to updated FBAR for Nine Nile Point Nuclear Station Unit i~incorporating Nods completed ri to 860101'7/g p,g DIBTRIBU DE: A053D C PIES ECEIVED: LTR ENCL SIZE: TITLE: OR Submi ttal: Updated FBAR (50.71)DOCKET 0 05000220 RECIPlENT ID CODE/NANE BWR ADTS BWR EICSB BWR PD1 LQ KELLY.J 0 BWR RSB COPIES LTTR ENCL 0 2 0 1 0 1 1 0 RECIPIENT ID CODE/NA{'{E BWR EB BWR FQB BWR PD1 PD BWR PSB COP IES LTTR ENCL 1 0 0 0 0 INTERNAL: REQ FILE 05 02 NRR ROE''l'l.L RQN1 06 EXTERNAL: DNB/DBB LPDR NSIC 1 1 1 1 FRANKLIN NRC PDR 03 1 1 1 TOTAL NUii{BER OF COPIEB REQUIRED: LTTR 20 ENCL 11 I 4)., II I II't~II 4 qM'I 1' NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE.N.Y.13202/TELEPHONE (315)474 1511 June 23, 1986 NMPl L 0071 Director of Nuclear Reactor Regulation Attention:
ACCESSION NBR: S60627026S         DQC. DATE:   86/06/23     NOTARIZED: YES           DOCKET 0 FACIL: 50-220 Nine Ni le Point Nuclear Stations           Unit   ii Niagara Poue 05000220 AUTH. NA{'{E         AUTHOR AFFILIATION NANQAN, C. V.     -
Mr.John A.Zwolinski, Project Director BWR Project Directorate Number 1 Division of BWR Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555 Re: Nine Mile Point Unit 1 Docket No.50-220 DPR-63
Niagara Nohawk Power Corp.
RECIP. NANE         RECIPIENT AFFILIATION ZWOLINBKliJ. A. BWR Pro Ject Directorate SUB JECT: Forwards Vals I   Zc I I to Rev 4 to updated         FBAR for Nine Nile Point Nuclear Station Unit i~ incorporating Nods completed ri to 860101 '7/g p,g DIBTRIBU           DE: A053D   C PIES     ECEIVED: LTR         ENCL     SIZE:
TITLE: OR Submi ttal: Updated     FBAR   (50. 71)
RECIPlENT           COPIES              RECIPIENT            COP IES ID CODE/NANE         LTTR ENCL         ID CODE/NA{'{E       LTTR ENCL BWR ADTS                        0      BWR EB                   1    0 BWR EICSB                2      0      BWR  FQB                       0 BWR PD1 LQ              1      0      BWR  PD1 PD                     0 KELLY. J      0        1      1      BWR PSB                       0 BWR RSB                        0 INTERNAL:                 05                       NRR ROE'' l'l. L REQ  FILE      02                      RQN1             06 EXTERNAL: DNB/DBB                   1      1      FRANKLIN                  1     1 LPDR                    1     1       NRC PDR           03     1 NSIC TOTAL NUii{BER OF COPIEB REQUIRED:       LTTR     20   ENCL       11


==Dear Mr.Zwolinski:==
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Niagara Mohawk Power Corporation hereby submits one (1)signed original and twelve (12)copies of Revision 4 to the Nine Mile Point Nuclear Station Unit 1 Final Safety Analysis Report (Updated).
NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474 1511 June 23, 1986 NMPl L 0071 Director of Nuclear Reactor Regulation Attention: Mr. John A. Zwolinski, Project Director BWR Project Directorate Number 1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re:    Nine Mile Point Unit      1 Docket No. 50-220 DPR-63
This revision supplies information on a replacement page basis, as indicated on Table l.A vertical bar indicates changes.Vertical bars were not placed next to figure changes;figure changes are indicated by revision numbers.In addition, Table 2 (attached) lists modifications made in accordance with lOCFR50.59 since the last submittal of the Final Safety Analysis Report (Updated)on June 27, 1985.Modifications completed prior to January 1, 1986 were reviewed and, if applicable, incorporated into the Final Safety Analysis Report (Updated).
 
Sincerely, NIAGARA MOHAWK POWER CORPORATION C.V.Manga Senior Vice President DPC:bd Attachments xc: Mr.Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY 12223 8606270268 860b23 PDR ADQCY 05000220 K PDR T~p UNITED STATES NUCLEAR REGULATORY COMMISSION
==Dear Mr. Zwolinski:==
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~)))In the Matter of)Niagara Mohawk Power Corporation
 
)(Nine Mile Point Unit 1)))))Docket No.50-220 AFFIDAVIT'.
Niagara Mohawk Power Corporation hereby submits one (1) signed original and twelve (12) copies of Revision 4 to the Nine Mile Point Nuclear Station Unit 1 Final Safety Analysis Report (Updated). This revision supplies information on a replacement page basis, as indicated on Table l. A vertical bar indicates changes. Vertical bars were not placed next to figure changes; figure changes are indicated by revision numbers.
V.Mangan,'eing duly sworn,'eposes and says: I am Senior Vice President of Niagara Mohawk Power Corporation,'uly authorized to act on the Corporation's behalf;as such, I have read the documents attached hereto and find that the statements made therein are true to the best of my knowledge, information and belief.C.V.Mangan Senior Vice President Niagara Mohawk Power Corporation Subscribed, acknowledged and sworn to before me on this~5 day of June, 1986.Quahn Notary Pu~c gggNNE AUST!N Y&
In addition, Table  2  (attached)  lists  modifications      made  in accordance with lOCFR50.59 since the last submittal of the Final Safety Analysis Report (Updated) on June 27, 1985. Modifications completed prior to January 1, 1986 were reviewed and,  if  applicable, incorporated into the Final Safety Analysis Report (Updated).
I tGI.'.~~>:,>j'~84,F)
Sincerely, NIAGARA MOHAWK POWER CORPORATION C. V. Manga Senior Vice President DPC:bd Attachments xc: Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY  12223 8606270268 860b23 PDR    ADQCY 05000220 K                    PDR
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t t NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT 1 Table 2-Modifications Implemented Under 10CFR50.59 Not Previously Submitted to the Nuclear Regulatory Commission*
T~
Mod.Number Modification Descri tion 78-04 78-21 80-90 81-27 81-36 82-03 Install nitrogen supply valve in Train 11 of the containment atmosphere dilution system Add welding outlets on elevation 198 of Reactor Buil ding Modify turbine generator sequential trip circuit by adding"motoring" relays to provide overspeed protection by verifying that all steam sources are closed off before opening turbine-generator breakers.Replace breathing air service water compressor
p
'Y'trainers with duplex strainers Install manual (normally locked-open) isolation valve in nitrogen supply line to containment atmospheric dilution system for maintenance.
 
Change detect zones (D-1114 8 DA-1114)H2 seal oil from Class A to Class B.Ref.NRC's SER to Amendment 30.Ir 82-33 Modify turbine thrust bearing wear detectors per GE technical information letter.82-57 82-69-1 82-69-3 Install Reactor Building sprinkler system drain tank level switch column isolation val-ve and testing tee.Provide level switch probe clearance and valve tee assembly for calibration.
UNITED STATES NUCLEAR REGULATORY COMMISSION
Upgrade the feedwater low flow control during startup, shutdown and hot standby to resolve NUREG-0619 feedwater nozzle cracking (thermal cycles)concerns.Also modified the motor driven feedwater recirculation system.Install redundant high pressure coolant injection initiation circuits for reliability.
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
*While some modifications may have been performed earlier, inclusion indi cates cl oseout of the entire modi f i cati on package.
                                                                                )
I I l II Page 2 Mod.Number Modification Descri tion 82-80-5 83-16 83-30 83-30-2 Revise logic on emergency condenser vent isolation valves to include confirmatory logic.Replace waste collector filter recycle pump with pump made by Gould.(Base and piping also modified).
                                                                                )
Original vendor (Delaval)no longer manufacturers this pump, which was leaking at the casing flange and could not be repaired.Replaced Turbine Building closed loop cooling heat exchangers ll 5 12.Replace closed loop cooling heat exchanger (part of 83-30 above)83-35 83-36 83-46 83-81 84-19 84-29 84-31 84-35 84-50 Addition of roof alarm (23')and camera at northwest wall of security annex.Additional document control (NSR)electrical outlets to support additional office space and equipment for records storage, drawing control room and computer tech shop.Prime computer;power upgrade-add 16 outlets (RM246-1)to accommodate additional computer peripherals and communications equipment.
                                                                                )
Upgrade Reactor Building fire barrier wall (NSR)piping penetration seals to 3 hour IEEE-634.Cut and relocate section of breathing air pipe so that post-LOCA vent line may be installed at Reactor Building El 281'.Accurex Upgrade-To provide reliable use of the fuel zone water level monitoring system hardware/software mod's per GE FDI NTCB.Replace the power cable to the reactor shutdown cooling system return line isolation valve motor-operator and DC valve board (outside the drywell.)with a larger cable to improve performance by minimizing motor burnout.Relocate 3 smoke detectors in digital computer room (auxiliary control room)to avoid discharge from air supply diffuser, per NRC Inpsection 84-06.Modify twelve input risers to Waste Disposal Building Sump 813 to minimize stoppage in floor drains and consequential contamination.
In the Matter of                                    )
P a Page 3 Mod.Number Modification Descri tion 84-51 84-004 85-012 Screen wash pump;replace with mechanical seals.Also changed butterfly valve to plug valve.Replace diesel fire pump governor inlet and discharge and pump bearing oil solenoid valves to provide manual start capability upon loss of power.Relocate supply voltage source for cleanup system isolation valves from powerboard 167 to 1618 8 171B and add thermal overload bypasses to satisfy environmental qualifications.
Niagara Mohawk Power Corporation                                         )                  Docket No. 50-220 (Nine Mile Point Unit 1)                                          )
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~0 NIAGARA MOHAWK POWER CORPORATION NINE, MILE POINT UNIT 1 FINAL SAFETY ANALYSIS REPORT (UPDATED)'EVISION 4.(1986)Table 1 Current Pa e Cover sheet,'olume I XXX1 II-25 V-29 V-.30 VI-21 VI-47;Tabl e VI-3A VI-50B, Table VI-3B VII-17 VII-21 VII-23 V I I-62 VIII-4 VIII-15 VI I I-21 VIII-68 X-32;Figure X-6 X-39 X-40, Figure X-7 X-52 X-62 XI I-19 Cover sheet, Volume II XXX1 XV-48 XV-54 XV-159 Re lacement Pa e(s)Cover sheet,'olume I XXX1 II-25 V-29 V-30 V-30A (New page)VI-21 VI-47, Tabl e VI-3A VI-50B, Table VI-3B VII-17 VI I-21 VI I-23 VII-62 VIII-4 VIII-15 VI I I-21 VIII-68 X-32, Figure X-6 X-39 X-40, Figure X-7 X-52 X-62 XII-19 Cover sheet, Volume II XXX1 XIII-9A (New page)XV-48 XV-54 XV-159 F~e I}}
                                                                                )
                                                                                )
AFFIDAVIT'.
V. Mangan,'eing duly sworn,'eposes                                  and says:
I  am    Senior Vice President of Niagara                                 Mohawk Power Corporation,'uly authorized to act                  on   the Corporation's behalf; as such, I have read the documents attached                    hereto and find that the statements                      made  therein are true to the best of                my    knowledge, information and                        belief.
C. V. Mangan Senior Vice President Niagara Mohawk Power Corporation Subscribed,             acknowledged and sworn to before                me on      this
~5              day    of June,          1986.
Quahn Notary        Pu      ~c gggNNE AUST!N                Y&
 
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t NIAGARA MOHAWK POWER CORPORATION t
NINE MILE POINT UNIT        1 Table 2
            - Modifications Implemented Under 10CFR50.59 Not Previously Submitted to the Nuclear Regulatory Commission*
Mod. Number                Modification Descri tion 78-04                      Install nitrogen supply valve in Train         11 of the containment atmosphere dilution system 78-21                      Add   welding outlets   on     elevation 198 of Reactor Buil ding 80-90                      Modify turbine generator sequential trip circuit by adding "motoring" relays to provide overspeed protection by verifying that all steam sources are closed off before opening turbine-generator breakers.
81-27                      Replace breathing     air service water compressor with duplex strainers                      'Y'trainers 81-36                        Install manual   (normally locked-open) isolation valve in nitrogen supply line to containment atmospheric dilution   system for maintenance.
82-03                      Change   detect zones (D-1114 8 DA-1114) H2 seal         oil from Class   A to Class B.       Ref. NRC's SER to Amendment 30.             Ir 82-33                       Modify turbine thrust bearing wear detectors per                     GE technical information         letter.
82-57                       Install Reactor Building sprinkler system drain tank level switch column isolation val-ve and testing tee.
Provide level switch probe clearance and valve tee assembly   for calibration.
82-69-1                      Upgrade the feedwater low flow control during startup, shutdown and hot standby to resolve NUREG-0619 feedwater nozzle cracking (thermal cycles) concerns.
Also modified the motor driven feedwater recirculation system.
82-69-3                      Install redundant high pressure coolant injection initiation circuits for reliability.
* While   some modifications may have been performed earlier, inclusion indi cates cl oseout of the entire modi fi cati on package.
 
I I l II
 
Page 2 Mod. Number Modification Descri tion 82-80-5     Revise logic on emergency condenser vent isolation valves to include confirmatory logic.
83-16      Replace waste collector     filter recycle pump with pump made by   Gould. (Base and piping also modified).
Original vendor (Delaval) no longer manufacturers this pump, which was leaking at the casing flange and could not be repaired.
83-30      Replaced Turbine Building closed loop cooling heat exchangers   ll 5 12.
83-30-2    Replace closed loop cooling heat exchanger       (part of 83-30 above) 83-35       Addition of roof alarm (23') and camera at northwest wall of security annex.
83-36      Additional document control (NSR) electrical outlets to support additional office space and equipment for records storage, drawing control room and computer tech shop.
83-46      Prime computer; power upgrade - add 16 outlets (RM246-1) to accommodate additional computer peripherals and communications equipment.
83-81      Upgrade Reactor     Building fire barrier wall (NSR) piping penetration seals to 3 hour IEEE-634.
84-19      Cut and relocate section of breathing       air pipe so that post-LOCA vent line may be installed       at Reactor Building   El 281'.
84-29      Accurex Upgrade     - To provide reliable use of the fuel zone water   level monitoring system hardware/software mod's per   GE   FDI NTCB.
84-31      Replace the power cable to the reactor shutdown cooling system return line isolation valve motor-operator and DC valve board (outside the drywell.) with a larger cable to improve performance by minimizing motor burnout.
84-35        Relocate 3 smoke detectors in digital computer room (auxiliary control room) to avoid discharge from air supply diffuser, per NRC Inpsection 84-06.
84-50      Modify twelve input risers to Waste Disposal Building Sump 813 to minimize stoppage in floor drains and consequential contamination.
 
P a
 
Page 3 Mod. Number Modification Descri tion 84-51       Screen wash pump; replace with mechanical seals. Also changed butterfly valve to plug valve.
84-004      Replace diesel fire pump governor inlet and discharge and pump bearing oil solenoid valves to provide manual start capability upon loss of power.
85-012      Relocate supply voltage source for cleanup system isolation valves from powerboard 167 to 1618 8 171B and add thermal overload bypasses to satisfy environmental qualifications.
 
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                ~                                     0 NIAGARA MOHAWK POWER CORPORATION NINE,MILE POINT UNIT     1 FINAL SAFETY ANALYSIS REPORT (UPDATED)
                        'EVISION   4 .(1986)
Table 1 Current     Pa e                         Re  lacement  Pa e(s)
Cover    sheet,'olume I                  Cover  sheet,'olume I XXX1                                      XXX1 II-25                                    II-25 V-29                                    V-29 V-.30                                   V-30 V-30A          (New page)
VI-21                                    VI-21 VI-47;     Tabl e VI-3A                  VI-47,    Tabl e VI-3A VI-50B,     Table VI-3B                   VI-50B,  Table VI-3B VII-17                                    VII-17 VII-21                                    VI I-21 VII-23                                    VI I-23 V I I-62                                 VII-62 VIII-4                                    VIII-4 VIII-15                                  VIII-15 VI I I-21                                VI I I-21 VIII-68                                  VIII-68 X-32;   Figure X-6                      X-32,  Figure X-6 X-39                                    X-39 X-40,   Figure X-7                     X-40,  Figure X-7 X-52                                    X-52 X-62                                    X-62 XI I-19                                  XII-19 Cover sheet,     Volume II              Cover sheet,    Volume  II XXX1                                     XXX1 XIII-9A      (New page)
XV-48                                    XV-48 XV-54                                    XV-54 XV-159                                   XV-159
 
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Revision as of 07:47, 30 October 2019

Forwards Vols I & II to Rev 4 to Updated FSAR for Nine Mile Point Nuclear Station Unit 1,incorporating Mods Completed Prior to 860101
ML17055B913
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/23/1986
From: Mangan C
NIAGARA MOHAWK POWER CORP.
To: Zwolinski J
Office of Nuclear Reactor Regulation
Shared Package
ML17055B914 List:
References
NMP1L-0071, NMP1L-71, NUDOCS 8606270268
Download: ML17055B913 (14)
v • d • e


Text

REGULATORY INFQR{'{ATION DISTR IBUTIQN SYSTEM (R IDS)

ACCESSION NBR: S60627026S DQC. DATE: 86/06/23 NOTARIZED: YES DOCKET 0 FACIL: 50-220 Nine Ni le Point Nuclear Stations Unit ii Niagara Poue 05000220 AUTH. NA{'{E AUTHOR AFFILIATION NANQAN, C. V. -

Niagara Nohawk Power Corp.

RECIP. NANE RECIPIENT AFFILIATION ZWOLINBKliJ. A. BWR Pro Ject Directorate SUB JECT: Forwards Vals I Zc I I to Rev 4 to updated FBAR for Nine Nile Point Nuclear Station Unit i~ incorporating Nods completed ri to 860101 '7/g p,g DIBTRIBU DE: A053D C PIES ECEIVED: LTR ENCL SIZE:

TITLE: OR Submi ttal: Updated FBAR (50. 71)

RECIPlENT COPIES RECIPIENT COP IES ID CODE/NANE LTTR ENCL ID CODE/NA{'{E LTTR ENCL BWR ADTS 0 BWR EB 1 0 BWR EICSB 2 0 BWR FQB 0 BWR PD1 LQ 1 0 BWR PD1 PD 0 KELLY. J 0 1 1 BWR PSB 0 BWR RSB 0 INTERNAL: 05 NRR ROE l'l. L REQ FILE 02 RQN1 06 EXTERNAL: DNB/DBB 1 1 FRANKLIN 1 1 LPDR 1 1 NRC PDR 03 1 NSIC TOTAL NUii{BER OF COPIEB REQUIRED: LTTR 20 ENCL 11

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NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474 1511 June 23, 1986 NMPl L 0071 Director of Nuclear Reactor Regulation Attention: Mr. John A. Zwolinski, Project Director BWR Project Directorate Number 1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63

Dear Mr. Zwolinski:

Niagara Mohawk Power Corporation hereby submits one (1) signed original and twelve (12) copies of Revision 4 to the Nine Mile Point Nuclear Station Unit 1 Final Safety Analysis Report (Updated). This revision supplies information on a replacement page basis, as indicated on Table l. A vertical bar indicates changes. Vertical bars were not placed next to figure changes; figure changes are indicated by revision numbers.

In addition, Table 2 (attached) lists modifications made in accordance with lOCFR50.59 since the last submittal of the Final Safety Analysis Report (Updated) on June 27, 1985. Modifications completed prior to January 1, 1986 were reviewed and, if applicable, incorporated into the Final Safety Analysis Report (Updated).

Sincerely, NIAGARA MOHAWK POWER CORPORATION C. V. Manga Senior Vice President DPC:bd Attachments xc: Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY 12223 8606270268 860b23 PDR ADQCY 05000220 K PDR

T~

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UNITED STATES NUCLEAR REGULATORY COMMISSION

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

)

)

)

In the Matter of )

Niagara Mohawk Power Corporation ) Docket No. 50-220 (Nine Mile Point Unit 1) )

)

)

)

AFFIDAVIT'.

V. Mangan,'eing duly sworn,'eposes and says:

I am Senior Vice President of Niagara Mohawk Power Corporation,'uly authorized to act on the Corporation's behalf; as such, I have read the documents attached hereto and find that the statements made therein are true to the best of my knowledge, information and belief.

C. V. Mangan Senior Vice President Niagara Mohawk Power Corporation Subscribed, acknowledged and sworn to before me on this

~5 day of June, 1986.

Quahn Notary Pu ~c gggNNE AUST!N Y&

I tGI .'.~~>:,>j'~84,F)

@ a~~ < >~4  %~3 fj~ ~(

t NIAGARA MOHAWK POWER CORPORATION t

NINE MILE POINT UNIT 1 Table 2

- Modifications Implemented Under 10CFR50.59 Not Previously Submitted to the Nuclear Regulatory Commission*

Mod. Number Modification Descri tion 78-04 Install nitrogen supply valve in Train 11 of the containment atmosphere dilution system 78-21 Add welding outlets on elevation 198 of Reactor Buil ding 80-90 Modify turbine generator sequential trip circuit by adding "motoring" relays to provide overspeed protection by verifying that all steam sources are closed off before opening turbine-generator breakers.

81-27 Replace breathing air service water compressor with duplex strainers 'Y'trainers 81-36 Install manual (normally locked-open) isolation valve in nitrogen supply line to containment atmospheric dilution system for maintenance.

82-03 Change detect zones (D-1114 8 DA-1114) H2 seal oil from Class A to Class B. Ref. NRC's SER to Amendment 30. Ir 82-33 Modify turbine thrust bearing wear detectors per GE technical information letter.

82-57 Install Reactor Building sprinkler system drain tank level switch column isolation val-ve and testing tee.

Provide level switch probe clearance and valve tee assembly for calibration.

82-69-1 Upgrade the feedwater low flow control during startup, shutdown and hot standby to resolve NUREG-0619 feedwater nozzle cracking (thermal cycles) concerns.

Also modified the motor driven feedwater recirculation system.

82-69-3 Install redundant high pressure coolant injection initiation circuits for reliability.

  • While some modifications may have been performed earlier, inclusion indi cates cl oseout of the entire modi fi cati on package.

I I l II

Page 2 Mod. Number Modification Descri tion 82-80-5 Revise logic on emergency condenser vent isolation valves to include confirmatory logic.

83-16 Replace waste collector filter recycle pump with pump made by Gould. (Base and piping also modified).

Original vendor (Delaval) no longer manufacturers this pump, which was leaking at the casing flange and could not be repaired.

83-30 Replaced Turbine Building closed loop cooling heat exchangers ll 5 12.

83-30-2 Replace closed loop cooling heat exchanger (part of 83-30 above) 83-35 Addition of roof alarm (23') and camera at northwest wall of security annex.

83-36 Additional document control (NSR) electrical outlets to support additional office space and equipment for records storage, drawing control room and computer tech shop.

83-46 Prime computer; power upgrade - add 16 outlets (RM246-1) to accommodate additional computer peripherals and communications equipment.

83-81 Upgrade Reactor Building fire barrier wall (NSR) piping penetration seals to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> IEEE-634.

84-19 Cut and relocate section of breathing air pipe so that post-LOCA vent line may be installed at Reactor Building El 281'.

84-29 Accurex Upgrade - To provide reliable use of the fuel zone water level monitoring system hardware/software mod's per GE FDI NTCB.

84-31 Replace the power cable to the reactor shutdown cooling system return line isolation valve motor-operator and DC valve board (outside the drywell.) with a larger cable to improve performance by minimizing motor burnout.

84-35 Relocate 3 smoke detectors in digital computer room (auxiliary control room) to avoid discharge from air supply diffuser, per NRC Inpsection 84-06.

84-50 Modify twelve input risers to Waste Disposal Building Sump 813 to minimize stoppage in floor drains and consequential contamination.

P a

Page 3 Mod. Number Modification Descri tion 84-51 Screen wash pump; replace with mechanical seals. Also changed butterfly valve to plug valve.84-004 Replace diesel fire pump governor inlet and discharge and pump bearing oil solenoid valves to provide manual start capability upon loss of power.85-012 Relocate supply voltage source for cleanup system isolation valves from powerboard 167 to 1618 8 171B and add thermal overload bypasses to satisfy environmental qualifications.

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~ 0 NIAGARA MOHAWK POWER CORPORATION NINE,MILE POINT UNIT 1 FINAL SAFETY ANALYSIS REPORT (UPDATED)

'EVISION 4 .(1986)

Table 1 Current Pa e Re lacement Pa e(s)

Cover sheet,'olume I Cover sheet,'olume I XXX1 XXX1 II-25 II-25 V-29 V-29 V-.30 V-30 V-30A (New page)

VI-21 VI-21 VI-47; Tabl e VI-3A VI-47, Tabl e VI-3A VI-50B, Table VI-3B VI-50B, Table VI-3B VII-17 VII-17 VII-21 VI I-21 VII-23 VI I-23 V I I-62 VII-62 VIII-4 VIII-4 VIII-15 VIII-15 VI I I-21 VI I I-21 VIII-68 VIII-68 X-32; Figure X-6 X-32, Figure X-6 X-39 X-39 X-40, Figure X-7 X-40, Figure X-7 X-52 X-52 X-62 X-62 XI I-19 XII-19 Cover sheet, Volume II Cover sheet, Volume II XXX1 XXX1 XIII-9A (New page)

XV-48 XV-48 XV-54 XV-54 XV-159 XV-159

F ~

e I

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