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{{#Wiki_filter:AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TEMPORARY FORM FROM'iagara Mohawk Power Corpo Syracuse~N.Y.13202 F J.Schneider DATE OF DOC: tion 8<<1-72 DATE REC'D 8.-4 2 LTR FI iRMO RPT To: Mr.Skovholt ORIG CC ('ENT AEC PDR~SENT LOCAL PDR CLASS: U PROP INFO DE IPTION: Ltr reporting an incident on 7-27-72~regarding an increasing recirculation syst va5W packing leakage within the drywell." No CYS REC'D ENCLOSURES:
{{#Wiki_filter:AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TEMPORARY FORM FI DATE OF DOC:      DATE REC'D    LTR    iRMO    RPT FROM'iagara             Mohawk Power Corpo       tion To:
DOCKET No: 0 220 PLANT NAMES: Nine Mble 00 NOT REMOVE II%NO'RFtIH Foa ACTION INFORMATION
Syracuse~
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J. Schneider Mr. Skovholt 13202 8<<1-72 ORIG        CC  ('ENT 8.-4   2
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                                                                                                ~
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AEC PDR SENT LOCAL PDR CLASS:                 U PROP INFO                               No CYS REC'D            DOCKET No:
~BOYD-L(Btla)
0 220 DE             IPTION:                                           ENCLOSURES:
DEYOUNG-L(PWR)
Ltr reporting         an incident   on 7-27-72~
~SKOVHOLT-L P.COLLINS REG OPR.SPILE Ih REGIOH (2)~ioRRIS v STEELE TECH REVIEW+HENDRXE g/SCHROEDER
regarding an increasing recirculation syst va5W packing leakage within the drywell."
~MACCARY LANGE PAWLICKX ,SHAO V KNUTH v'TELLO iMO ORE~THOMPSON>TEDESCO v LONG~LAINAS BENAROYA lr VOLL14ER~ENTON (4)GRXMES GAMMXLL KASTNER BALI JQU)FINE EHVIRO MOLL?R DICKER KNIGHTON YOUNGBIOOD
00 NOT REMOVE PLANT NAMES:             Nine Mble II%NO'RFtIH Foa ACTION INFORMATION           -   2           AB BUTLER         L          KNIEL L                VASSALLO L            ZIEMANN L             KNIGHTON ENVIRO W/ Copies                  W/ Copies               W/ Copies             W/ 9 Copies           W/   Copies CLARK(L)                    SCHWENCER(L)          H. DENTON              CHITtAtOOD(FM)
'RO JL'CT LEADER HARLESS PSM SMILEX NUSSBAUMER LIC ASST.SERVICE MASON WIISON KARI SMITH GEARIN DXGGS TEETS WADE SHAFER BROWN JAP IHD BRAITMAN SALT ZMAN PIAHS MODOHALD DUDE C~MILES~1-'LOCAL PDR Oswe o N Y~l-mIE(LAUGHL-.N Vl<<NSIC(BUCHANAN) 1-ASLB-Yoaz/SAYRE WOODWARD/HE ST.~16 CYS ACRS HOLDING EXTERNAL DXSTBIBUTXON (X (5)(9)-NATIONAL LAB>s ANL/ORNL/PNL 1-R.CARROLL-OC~
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W/ Copies                 W/ Copies             W/-=-Copies- -=-- =-- W/ -=Copies           W/   Copies iNTERNAL DISTRXBUTION G                             TECH REVIEW        lr VOLL14ER            HARLESS              WADE HAEC                 PDR                 +HENDRXE              ~ENTON (4)                                  SHAFER VOGCp                 ROOM P-506A       g/SCHROEDER              GRXMES              PSM                  BROWN WNi&i'TZING/STAr(('ASE
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                                            ~ MACCARY                GAMMXLL              SMILEX LANGE                KASTNER              NUSSBAUMER          JAP IHD GIAl4BUSSO                           PAWLICKX              BALIJQU)                                  BRAITMAN
Ffte Cy-..NIAGARA~&#x17d;MOHAWK 300 ERIE 8OUI EVARD WEST SYRACUSE, H.Y.IS202 NIAGARA MOHAWK POWER CORPORATION August 1, 1972 Mr.Donald J.Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing United States Atomic Energy Commission Washington, D.C.20545 8
  ~ BOYD-L(Btla)                             ,SHAO                  FINE                LIC ASST.            SALTZMAN DEYOUNG-L(PWR)                     V  KNUTH                                      SERVICE
  ~ SKOVHOLT-L                               v'TELLO                  EHVIRO              MASON                PIAHS P. COLLINS                           iMOORE                MOLL?R              WIISON              MODOHALD REG OPR
                                            ~> THOMPSON TEDESCO DICKER              KARI                DUDE KNIGHTON            SMITH
.SPILE Ih                   REGIOH (2)     v LONG                  YOUNGBIOOD          GEARIN              C~ MILES
  ~ioRRIS                                    ~ LAINAS                   JL'CT LEADER
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  ~1-'LOCAL PDR                     Oswe o     N Y
  ~Vl<<NSIC(BUCHANAN) l-mIE(LAUGHL-.N                                        (X (5)(9)-NATIONAL LAB>s               1-PDR-SAN/LA/NY, ANL/ORNL/PNL               1- GERALD LELLUCHE 1-ASLB-Yoaz/SAYRE                                                1-R. CARROLL-OC~ GT B327       BROOKHAVEN NAT. LAB WOODWARD/HE ST.                                            1>>R. CATLIN) A-170-GT         1 BOLANDp IDAHO FALLS~
~16            CYS ACRS HOLDING                                          1 CONSULANT'S                    IDAHO(50>>331 Only)
NEWMARK/BLUAA/AGABIAN      l-aD.. mrzza   .. F-3o9GT


==Dear Mr.Skovholt:==
F
Re: Provisional Operating License: DPR-17 Docket No.: 50-220 Appendix A (Technical Specifications 3.3.1 a and 3.3.1 b)of Provisional Operating License DPR-17 for Nine Mile Point Nuclear Station, Unit Ol states: 3.3.1 a"After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than five percent oxygen with nitrogen gas whenever the reactor coolant pressure is greater than 110 psig and the reactor is in the power operating condition, except as.specified in"b" below." 3.3.1 b"Within the 24 hour period subsequent to increase of the reactor coolant pressure above 110 psig whenever the reactor is in the power.operating conditj.on, the containment atmosphere oxygen concentration shall be reduced to less than five percent by weight and maintained in this con-dition.Deinerting was commenced 24 hours prior to a major refueling outage or other scheduled shutdown." An orderly shutdown of Unit 81, Nine Mile Point Nuclear Station was begun on July 27, 1972 due to increasing recirculation system valve packing leakage within the drywell.Following repacking of the affected valves, the unit was restarted on July 30, 1972 and reached 110 psig at 0700 that day.  
                            ~ ~
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Mx.Donald J.Skovho1t United States Atomic Energy Commission 0 Page 2 An agreement had been made prior to shutdown with National Cylinder Gas, a nitrogen gas supplier in Conshohocken, Pa.for delivery of two trucks of nitrogen on July 30, 1972.Normal inerting requires 4-6 hours and could easily be accomplished that day, well within the required 24 hours.However, unknown to station personnel, the gas supplier was having difficulty in obtaining drivers for the necessary two trucks of nitrogen.The startup of the Unit beyond 110 psig continued, based upon the prior agreement that nitrogen would be arriving for inerting that day.At midnight, July 30, 1972 with no nitrogen for inerting on site, it was deemed necessary by station personnel to hold thermal power to 1200 MN(t)and not continue with the normal scheduled startup until the drywell was inerted.The first truck of nitrogen arrived at the station the morning of July 31, 1972 and inerting began immediately.
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The drywell atmosphere was reduced to less than five percent oxygen at 134S that day, reaching 3.9 percent at 1400.The start up scheduled then continued.
                        -*
The drywell atmosphere remained within specification following inerting and with the arrival of the second truck late in the evening, July 31, 1972 was reduced to its present level of one percent by weight of oxygen.Very truly yours, F.J.Schn'eider Vice President e Operations 1 t l l J t}}
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                ~~am b 300 ERIE 8OUI EVARD WEST SYRACUSE, H.Y. IS202 j
August 1, 1972 Mr. Donald J. Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing                                                          8 United States Atomic Energy Commission Washington, D. C.      20545
 
==Dear Mr. Skovholt:==
 
Re:       Provisional Operating License:         DPR-17 Docket No.: 50-220 Appendix A (Technical Specifications 3.3.1 a and 3.3.1 b) of Provisional Operating License DPR-17 for Nine Mile Point Nuclear Station, Unit Ol states:
3.3.1     a "After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than five percent oxygen with nitrogen gas whenever the reactor coolant pressure is greater than 110 psig and the reactor is in the power operating condition, except as. specified in "b" below."
3.3.1     b "Within the 24 hour period subsequent to increase of the reactor coolant pressure above 110 psig whenever the reactor is in the power. operating conditj.on, the containment atmosphere oxygen concentration shall be reduced to less than five percent by weight and maintained in this con-dition. Deinerting was commenced 24 hours prior to a major refueling outage or other scheduled shutdown."
An     orderly shutdown of Unit 81, Nine Mile Point Nuclear           Station was begun on July 27, 1972 due to increasing recirculation system               valve packing leakage within the drywell. Following repacking of the                 affected valves, the unit was restarted on July 30, 1972 and reached 110               psig at 0700 that day.
 
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  ~ ~ ~ ~
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            ~   ~
 
0 Mx. Donald   J. Skovho1t                                                   Page 2 United States Atomic Energy Commission An agreement   had been made prior to shutdown with National Cylinder Gas, a nitrogen gas supplier in Conshohocken, Pa. for delivery of two trucks of nitrogen on July 30, 1972. Normal inerting requires 4 - 6 hours and could easily be accomplished that day, well within the required 24 hours. However, unknown to station personnel, the gas supplier was having difficulty in obtaining drivers for the necessary two trucks of nitrogen. The startup of the Unit beyond 110 psig continued, based upon the prior agreement that nitrogen would be arriving for inerting that day. At midnight, July 30, 1972 with no nitrogen for inerting on site,     it was deemed necessary by station personnel   to hold thermal power to 1200 MN(t) and not continue with the normal scheduled startup   until the drywell was inerted.
The first truck of nitrogen arrived at the station the morning of July 31,       1972 and inerting began immediately. The drywell atmosphere was reduced to less than five percent oxygen at 134S that day, reaching 3.9 percent at 1400.
The start up scheduled   then continued.
The drywell atmosphere remained within specification following inerting       and with the arrival of the second truck late in the evening, July 31, 1972       was reduced to its present level of one percent by weight of oxygen.
Very truly yours, F. J. Schn'eider Vice President   e Operations
 
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Revision as of 08:09, 30 October 2019

Letter Reporting an Orderly Shutdown on July 27, 1972 Due to Increasing Recirculation System Valve Packing Leakage within the Drywell
ML17037C130
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/01/1972
From: Schneider F
Niagara Mohawk Power Corp
To: Skovholt D
US Atomic Energy Commission (AEC)
References
Download: ML17037C130 (6)
v • d • e


Text

AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TEMPORARY FORM FI DATE OF DOC: DATE REC'D LTR iRMO RPT FROM'iagara Mohawk Power Corpo tion To:

Syracuse~

F N. Y.

J. Schneider Mr. Skovholt 13202 8<<1-72 ORIG CC ('ENT 8.-4 2

~

AEC PDR SENT LOCAL PDR CLASS: U PROP INFO No CYS REC'D DOCKET No:

0 220 DE IPTION: ENCLOSURES:

Ltr reporting an incident on 7-27-72~

regarding an increasing recirculation syst va5W packing leakage within the drywell."

00 NOT REMOVE PLANT NAMES: Nine Mble II%NO'RFtIH Foa ACTION INFORMATION - 2 AB BUTLER L KNIEL L VASSALLO L ZIEMANN L KNIGHTON ENVIRO W/ Copies W/ Copies W/ Copies W/ 9 Copies W/ Copies CLARK(L) SCHWENCER(L) H. DENTON CHITtAtOOD(FM)

W/ Copies W/ Copies W/ Copies W/ Copies W/ Copies GOLLER(L) STOLZ(L) SCHEMEL (L ) DICKER(ENVIRO)

W/ Copies W/ Copies W/-=-Copies- -=-- =-- W/ -=Copies W/ Copies iNTERNAL DISTRXBUTION G TECH REVIEW lr VOLL14ER HARLESS WADE HAEC PDR +HENDRXE ~ENTON (4) SHAFER VOGCp ROOM P-506A g/SCHROEDER GRXMES PSM BROWN WNi&i'TZING/STAr(('ASE

~ MACCARY GAMMXLL SMILEX LANGE KASTNER NUSSBAUMER JAP IHD GIAl4BUSSO PAWLICKX BALIJQU) BRAITMAN

~ BOYD-L(Btla) ,SHAO FINE LIC ASST. SALTZMAN DEYOUNG-L(PWR) V KNUTH SERVICE

~ SKOVHOLT-L v'TELLO EHVIRO MASON PIAHS P. COLLINS iMOORE MOLL?R WIISON MODOHALD REG OPR

~> THOMPSON TEDESCO DICKER KARI DUDE KNIGHTON SMITH

.SPILE Ih REGIOH (2) v LONG YOUNGBIOOD GEARIN C~ MILES

~ioRRIS ~ LAINAS JL'CT LEADER

'RO DXGGS v STEELE BENAROYA TEETS EXTERNAL DXSTBIBUTXON

~1-'LOCAL PDR Oswe o N Y

~Vl<<NSIC(BUCHANAN) l-mIE(LAUGHL-.N (X (5)(9)-NATIONAL LAB>s 1-PDR-SAN/LA/NY, ANL/ORNL/PNL 1- GERALD LELLUCHE 1-ASLB-Yoaz/SAYRE 1-R. CARROLL-OC~ GT B327 BROOKHAVEN NAT. LAB WOODWARD/HE ST. 1>>R. CATLIN) A-170-GT 1 BOLANDp IDAHO FALLS~

~16 CYS ACRS HOLDING 1 CONSULANT'S IDAHO(50>>331 Only)

NEWMARK/BLUAA/AGABIAN l-aD.. mrzza .. F-3o9GT

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August 1, 1972 Mr. Donald J. Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing 8 United States Atomic Energy Commission Washington, D. C. 20545

Dear Mr. Skovholt:

Re: Provisional Operating License: DPR-17 Docket No.: 50-220 Appendix A (Technical Specifications 3.3.1 a and 3.3.1 b) of Provisional Operating License DPR-17 for Nine Mile Point Nuclear Station, Unit Ol states:

3.3.1 a "After completion of the startup test program and demonstration of plant electrical output, the primary containment atmosphere shall be reduced to less than five percent oxygen with nitrogen gas whenever the reactor coolant pressure is greater than 110 psig and the reactor is in the power operating condition, except as. specified in "b" below."

3.3.1 b "Within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to increase of the reactor coolant pressure above 110 psig whenever the reactor is in the power. operating conditj.on, the containment atmosphere oxygen concentration shall be reduced to less than five percent by weight and maintained in this con-dition. Deinerting was commenced 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a major refueling outage or other scheduled shutdown."

An orderly shutdown of Unit 81, Nine Mile Point Nuclear Station was begun on July 27, 1972 due to increasing recirculation system valve packing leakage within the drywell. Following repacking of the affected valves, the unit was restarted on July 30, 1972 and reached 110 psig at 0700 that day.

)

~ ~ ~ ~

I 4

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~ ~

0 Mx. Donald J. Skovho1t Page 2 United States Atomic Energy Commission An agreement had been made prior to shutdown with National Cylinder Gas, a nitrogen gas supplier in Conshohocken, Pa. for delivery of two trucks of nitrogen on July 30, 1972. Normal inerting requires 4 - 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and could easily be accomplished that day, well within the required 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, unknown to station personnel, the gas supplier was having difficulty in obtaining drivers for the necessary two trucks of nitrogen. The startup of the Unit beyond 110 psig continued, based upon the prior agreement that nitrogen would be arriving for inerting that day. At midnight, July 30, 1972 with no nitrogen for inerting on site, it was deemed necessary by station personnel to hold thermal power to 1200 MN(t) and not continue with the normal scheduled startup until the drywell was inerted.

The first truck of nitrogen arrived at the station the morning of July 31, 1972 and inerting began immediately. The drywell atmosphere was reduced to less than five percent oxygen at 134S that day, reaching 3.9 percent at 1400.

The start up scheduled then continued.

The drywell atmosphere remained within specification following inerting and with the arrival of the second truck late in the evening, July 31, 1972 was reduced to its present level of one percent by weight of oxygen.

Very truly yours, F. J. Schn'eider Vice President e Operations

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