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{{#Wiki_filter:NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT¹1 Narrative of 0 eratin Ex erience August 1978 The unit operated at 80;8~o capacity factor with an availability of 95.9~o for the month.The month began with unit derated to 94~~Core Thermal Power due to scram reactivity considerations; the unit was at 94~a power on August 1.Control Rod withdrawals were used to maintain power/flow position of 94~~CTP when at 0110 on August 3 a reactor scram occurred due to high flux because of a problem encountered while testing MSIV's.The scram was attributed to either operator error or a hung-up relay in the test circuit.Many tests were conducted but no malfunctions could be found.A plant start-up was commenced at 1345 with reactor critical at 1650 and on the line at 0655 on August 4.Continued startup and load increases reaching 450 MWe by 2230.The following day after awaiting Xe build-up, reduced load to 375 MWe for setting final rod pattern.Load was sub-sequently increased to 430 MWe by 1710, and load increases at the pre-conditioning rate of 3 MWe/hr were initiated.
{{#Wiki_filter:NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT       ¹1 Narrative of   0 eratin   Ex   erience August 1978 The unit operated at   80;8~o capacity factor with an availability of 95.9~o for the month.
On Monday August 7, station output was approximately 540 MWe with preconditioning ramp rate still in effect.Completed an LPRM calibration on August 8, and reached preconditioned envelope to 1711 MWt on the 9th of August;also started power rod withdrawals to maintain 94~o CTP (553 MWe).Reduced load to 500 MWe at 2230 on 11th of August in order to re-place seals on¹11 motor driven feedwater pump.Load recovered to 540 MWE at 2230 the following day upon completion of pump work, and output of 554 MWe attained at 0800 on the 13th of August.Unit operated at approximately 94'o CTP by rod withdrawal until 2200 on the 19th when a reduction to 450 MWe via reactor recirculation flow occurred in order to withdraw shallow control rods.Preconditioning from 461 MWe was initiated and station output of 537 MWe was reached at 0540 on August 21.Unit operated at this power level until August 27 when a coast down to 92~o CTP was initiated, to meet new power/flow limitations based on scram reactivity considerations.
The month began   with unit derated to     94~~ Core Thermal Power due to scram   reactivity considerations; the unit     was   at 94~a power on August 1.
However, a further reductions to approximately 80>~power was required when¹11 Reactor Recirculating Pump had to be taken out of service at 1735 due to a pump cooler leak.The plant was derated to 84'o CTP from the 27th through the end of the month, and output was at approximately 485 MWe during this period.  
Control   Rod withdrawals were used to maintain power/flow position of 94~~ CTP   when at 0110 on August 3 a reactor scram occurred due to high flux because of a problem encountered while testing MSIV's. The scram was attributed to either operator error or a hung-up relay in the test circuit. Many tests were conducted but no malfunctions could be found.
', 4 e SIt'C 0S REGULATORY INFORNATION DISTRIBUTION SYSTEN<RIBS)DISTRIBUTION FOR INCONING NATERIAL~80-220'%CYANIC'l@Hkwk (wR NOTARIZED:
A plant start-up was commenced       at 1345 with reactor     critical at 1650 and on the line at 0655 on August       4. Continued startup and load increases reaching 450 MWe by 2230. The following day after awaiting Xe build-up, reduced load to 375 MWe for setting final rod pattern. Load was sub-sequently increased to 430 MWe by 1710, and load increases at the pre-conditioning rate of 3 MWe/hr were initiated.
NO EKE'kS D".0NI/i7)78 MCTYPE: I ETTER COPIES RECEIVED  
On Monday   August 7, station output was approximately 540 MWe with preconditioning     ramp rate still in effect. Completed an LPRM calibration on August 8, and reached     preconditioned envelope to 1711 MWt on the 9th of August; also started power rod withdrawals to maintain 94~o CTP (553   MWe) .
Reduced load to 500 MWe at 2230 on 11th of August in order to re-place seals on &#xb9;11 motor driven feedwater pump. Load recovered to 540             MWE at 2230 the following day upon completion of pump work, and output of 554 MWe attained at 0800 on the 13th of August.
Unit operated at approximately 94'o CTP by rod withdrawal until 2200 on   the 19th when a reduction to 450 MWe via reactor recirculation flow occurred in order to withdraw shallow control rods. Preconditioning from 461 MWe was initiated and station output of 537 MWe was reached at 0540 on August 21. Unit operated at this power level until August 27 when a coast down to 92~o CTP was initiated, to meet new power/flow limitations based on scram reactivity considerations.         However, a further reductions to approximately 80>~ power was required when &#xb9;11 Reactor Recirculating Pump had to be taken out of service at 1735 due to a pump cooler leak.
The plant was derated to 84'o CTP from the 27th through the end of the month, and output was at approximately 485 MWe during this period.
 
4
  ',
 
e     SIt'C 0S REGULATORY INFORNATION DISTRIBUTION SYSTEN <RIBS)
DISTRIBUTION FOR INCONING NATERIAL                                           ~80-220
                                                    '%CYANIC'l@Hkwk (   wR                 EKE'kS D".0NI/i7)78 MCTYPE: I ETTER             NOTARIZED: NO                                                    COPIES RECEIVED


==SUBJECT:==
==SUBJECT:==
LTR i ENCL i ORWARDING SUBJECT FACILITY'NONTHLY OPERATING REPT FOR THE NONTI"I OF JULY'978.~iWH W/L8'r~1 DISTR I I N I T I AL: DISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS++<+444~+<<<+<<<++
LTR i   ENCL i ORWARDING SUBJECT FACILITY' NONTHLY OPERATING REPT FOR THE NONTI"I OF JULY' 978.
ANNUAL'ENI-ANNUAL 5 NONTHLY OPERATING RPTS.<QL STAGE)<DISTRIBUTION CODE A008>FOR ACTION: INTERNAL: BR CHIEF ORBN3 BC+>M/6 ENCL REG FILE)~M/ENCL I-L E+4Q/2 ENCL HANAUER~H~M/ENCL AD FOR 8YS ou PRO J'~py M/ENCL REACTOR SAFETY BR++M/ENCL EEB~~W/ENCL EFFLUFNT TRFAT SYS><>M/ENCL NRC PDR++M/ENCL NIPC+<H/2 ENCL DIRECTOR DOR>4M/ENCL ENGINFERING BR+%M/ENCL PLANT SYSTEMS BR>4M/ENCL CORE PERFORNANCE BR+~M/ENCL EXTERNAL: LPDR'S OSMEGOi NY<F~M/ENCL NATL LAB ANL~~uM/ENCL TERA~~@l/ENCL NSI C+%M/ENCL ACRS CAT B<~~Wr 15 ENCL DISTRIBUTION:
          ~iWH W/L8'r             ~1 DISTR I       I N I T I AL:
LTR 4i ENCL 4i SIZE: iP+4P h 0HHHHF8H(3HI+HFHHFHPHFHFHF+N)t 8f 8F8'.8f 40fdl+dl 68HFgf-Hat CONTROL NBR: 782i90036 THE END 8f%8f.%%%%%%%%%%%%%%%%%%%
DISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS ++<+444~+<<<+<<<++
k%%%%%%%%%c 0 1 It V&#xc3;Il&SABB g ppgG@gqnyg NWP-0185 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y.13202/TELEPHONE (315)474-1511 Auguek 7, 1978 NJLe~/L 0(gee o)hfanagemeet'nfo/Im~n and Paog/Iam Co~oL U~ed S~e5 NucLea/L ReguLatocg CommLwmn Olae&ngkon, V.C.20555 RE: 'Dock&No.50-220 8PR-63 Gentlemen:
ANNUAL'ENI-ANNUAL5                        NONTHLY OPERATING RPTS .<QL STAGE)
Sub~ed he/L~h~Xhe RepoM o)Ope/c~ng$~&cb and S~oI0n Expetu.ence
    <DISTRIBUTION CODE A008>
$o/L 3'uLI/1978)o/L We N~e h4Le Pokery NucLea/L S~on U~ill.ALeo LneLudedks a Na/vIative RepoM o(Oping Expetu,ence (o/L She mort'h.Ve/Ly~I/you/L6, xc: Sme~/L, O(g.e,e os 78E (10 eop~e5)NRC Regin'i OlI/~e (1 copy)Thomas E.Lempge5 Gene/IaL Supetu'.etendeet-NueLea/L Gene/cation R.R.SchneLde/L VLce Pae5&eet-ELe~e Prcodu~on (s 782190036 f}}
FOR ACTION:               BR CHIEF ORBN3 BC+>M/6 ENCL INTERNAL:                REG         FILE)~M/ENCL                          NRC PDR++M/ENCL I-L E+4Q/2              ENCL                    NIPC+<H/2 ENCL HANAUER~H~M/ENCL                                  DIRECTOR DOR>4M/ENCL AD FOR 8YS ou PRO J'~py M/ENCL                   ENGINFERING BR+%M/ENCL REACTOR SAFETY BR++M/ENCL                         PLANT SYSTEMS BR>4M/ENCL EEB~~W/ENCL                                      CORE PERFORNANCE BR+~M/ENCL EFFLUFNT TRFAT SYS><>M/ENCL EXTERNAL:                 LPDR'S OSMEGOi         NY<F~M/ENCL NATL LAB ANL~~uM/ENCL TERA~~@l/ENCL NSI C+%M/ENCL ACRS           CAT B<~~Wr 15 ENCL DISTRIBUTION:           LTR     4i           ENCL     4i                         CONTROL NBR:    782i90036 SIZE: iP+4P h
0HHHHF8H( 3HI+HFHHFHPHFHFHF+N )t 8f 8F8'.8f 40fdl+dl 68HFgf-Hat THE END   8f%8f.%%%%%%%%%%%%%%%%%%% k%%%%%%%%%c
 
0 1
 
It V &#xc3;Il&SABB g ppgG@gqnyg                                                         NWP-0185 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Auguek 7, 1978 NJLe~/L 0(gee o) hfanagemeet'nfo/Im~n and Paog/Iam Co~oL U~ed S~e5       NucLea/L ReguLatocg CommLwmn Olae&ngkon, V.C.       20555 RE:   'Dock& No. 50-220 8PR-63 Gentlemen:
Sub~ed he/L~h S~oI0n Expetu.ence $ o/L
                            ~  Xhe RepoM 3'uLI/ 1978 )o/L o) Ope/c~ng $    ~&cb We N~e h4Le Pokery and NucLea/L S~on U~ ill.
ALeo LneLudedks a     Na/vIative RepoM o(     Oping         Expetu,ence (o/L She mort'h.
Ve/Ly ~I/     you/L6, Thomas E. Lempge5 Gene/IaL Supetu'.etendeet-NueLea/L Gene/cation R.R. SchneLde/L VLce Pae5&eet-ELe~e     Prcodu~on xc:  Sme~/L, O(g.e,e os      78E (10 eop~e5)
NRC Regin 'i OlI/~e      (1 copy)
(s 782190036
 
f}}

Revision as of 08:19, 30 October 2019

Letter Submitting the July 1978 Report of Operating Statistics, Shutdown Experience, and a Narrative Report of Operating Experiences
ML17037B742
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/07/1978
From: Lempges T, Schneider R
Niagara Mohawk Power Corp
To:
Office of Nuclear Reactor Regulation
References
Download: ML17037B742 (6)


Text

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT ¹1 Narrative of 0 eratin Ex erience August 1978 The unit operated at 80;8~o capacity factor with an availability of 95.9~o for the month.

The month began with unit derated to 94~~ Core Thermal Power due to scram reactivity considerations; the unit was at 94~a power on August 1.

Control Rod withdrawals were used to maintain power/flow position of 94~~ CTP when at 0110 on August 3 a reactor scram occurred due to high flux because of a problem encountered while testing MSIV's. The scram was attributed to either operator error or a hung-up relay in the test circuit. Many tests were conducted but no malfunctions could be found.

A plant start-up was commenced at 1345 with reactor critical at 1650 and on the line at 0655 on August 4. Continued startup and load increases reaching 450 MWe by 2230. The following day after awaiting Xe build-up, reduced load to 375 MWe for setting final rod pattern. Load was sub-sequently increased to 430 MWe by 1710, and load increases at the pre-conditioning rate of 3 MWe/hr were initiated.

On Monday August 7, station output was approximately 540 MWe with preconditioning ramp rate still in effect. Completed an LPRM calibration on August 8, and reached preconditioned envelope to 1711 MWt on the 9th of August; also started power rod withdrawals to maintain 94~o CTP (553 MWe) .

Reduced load to 500 MWe at 2230 on 11th of August in order to re-place seals on ¹11 motor driven feedwater pump. Load recovered to 540 MWE at 2230 the following day upon completion of pump work, and output of 554 MWe attained at 0800 on the 13th of August.

Unit operated at approximately 94'o CTP by rod withdrawal until 2200 on the 19th when a reduction to 450 MWe via reactor recirculation flow occurred in order to withdraw shallow control rods. Preconditioning from 461 MWe was initiated and station output of 537 MWe was reached at 0540 on August 21. Unit operated at this power level until August 27 when a coast down to 92~o CTP was initiated, to meet new power/flow limitations based on scram reactivity considerations. However, a further reductions to approximately 80>~ power was required when ¹11 Reactor Recirculating Pump had to be taken out of service at 1735 due to a pump cooler leak.

The plant was derated to 84'o CTP from the 27th through the end of the month, and output was at approximately 485 MWe during this period.

4

',

e SIt'C 0S REGULATORY INFORNATION DISTRIBUTION SYSTEN <RIBS)

DISTRIBUTION FOR INCONING NATERIAL ~80-220

'%CYANIC'l@Hkwk ( wR EKE'kS D".0NI/i7)78 MCTYPE: I ETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR i ENCL i ORWARDING SUBJECT FACILITY' NONTHLY OPERATING REPT FOR THE NONTI"I OF JULY' 978.

~iWH W/L8'r ~1 DISTR I I N I T I AL:

DISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS ++<+444~+<<<+<<<++

ANNUAL'ENI-ANNUAL5 NONTHLY OPERATING RPTS .<QL STAGE)

<DISTRIBUTION CODE A008>

FOR ACTION: BR CHIEF ORBN3 BC+>M/6 ENCL INTERNAL: REG FILE)~M/ENCL NRC PDR++M/ENCL I-L E+4Q/2 ENCL NIPC+<H/2 ENCL HANAUER~H~M/ENCL DIRECTOR DOR>4M/ENCL AD FOR 8YS ou PRO J'~py M/ENCL ENGINFERING BR+%M/ENCL REACTOR SAFETY BR++M/ENCL PLANT SYSTEMS BR>4M/ENCL EEB~~W/ENCL CORE PERFORNANCE BR+~M/ENCL EFFLUFNT TRFAT SYS><>M/ENCL EXTERNAL: LPDR'S OSMEGOi NY<F~M/ENCL NATL LAB ANL~~uM/ENCL TERA~~@l/ENCL NSI C+%M/ENCL ACRS CAT B<~~Wr 15 ENCL DISTRIBUTION: LTR 4i ENCL 4i CONTROL NBR: 782i90036 SIZE: iP+4P h

0HHHHF8H( 3HI+HFHHFHPHFHFHF+N )t 8f 8F8'.8f 40fdl+dl 68HFgf-Hat THE END 8f%8f.%%%%%%%%%%%%%%%%%%% k%%%%%%%%%c

0 1

It V ÃIl&SABB g ppgG@gqnyg NWP-0185 NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Auguek 7, 1978 NJLe~/L 0(gee o) hfanagemeet'nfo/Im~n and Paog/Iam Co~oL U~ed S~e5 NucLea/L ReguLatocg CommLwmn Olae&ngkon, V.C. 20555 RE: 'Dock& No. 50-220 8PR-63 Gentlemen:

Sub~ed he/L~h S~oI0n Expetu.ence $ o/L

~ Xhe RepoM 3'uLI/ 1978 )o/L o) Ope/c~ng $ ~&cb We N~e h4Le Pokery and NucLea/L S~on U~ ill.

ALeo LneLudedks a Na/vIative RepoM o( Oping Expetu,ence (o/L She mort'h.

Ve/Ly ~I/ you/L6, Thomas E. Lempge5 Gene/IaL Supetu'.etendeet-NueLea/L Gene/cation R.R. SchneLde/L VLce Pae5&eet-ELe~e Prcodu~on xc: Sme~/L, O(g.e,e os 78E (10 eop~e5)

NRC Regin 'i OlI/~e (1 copy)

(s 782190036

f