ML20064B849
| ML20064B849 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/29/1978 |
| From: | Gronberg W POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| JNRC-48, NUDOCS 7810110156 | |
| Download: ML20064B849 (18) | |
Text
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POWER AUTHORITY OF THE.' STATE OF NEW YORK 10 COLUMBUS CIRCLE Niw YORx. N. Y.10019 (212) 397-6200
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"".g" C,R,AN N. JR JNRC-48 WO M AS, Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Tramas A. Ippolito, Chief OperaEng Reactors Branch No. 3 Division of Operating Reactors
Subject:
James A. FitzPatrick Nucleah Power Plant Bases for Suppression Pool Temperature Transient Analysis Docket No. 50-333
Dear Sir:
The Power Authority is in receipt of your letter (R. W. Reid letter to G. T. Berry dated December 9,1977) which requested t
plant-specific information for the James A. FitzPatrick Nuclear Power Plant related to suppression pool temperature transients and the suppression pool temperature monitoring system. The Authority has reviewed your request with General Electric Company in order to provide a technically justifiable bases upon which sup-I pression pool temperature transient analyses could be performed.
l This review has generated proposed analysis cases with initial con-i ditions, event descriptions and assumptions defined. These proposed cases are being submitted as Attachment A, while Attachment B des-cribes the suppression pool monitoring system now in use at the plant.
1 By letter dated December 29,1977 to the Commission, the Authority committed to a projected submittal date of September 30,1978 for the l
plant specific information. However, due to the large number of oper-l ating plants that require such analyses, General Electric has advised I
us that the analyses results could be submitted six (6) months after agree-1 opp ment has been reached with the Commission on the proposed analyses bases enclosed in this letter.
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As indicated in your letter, the information requested is intended l
to serve as part of the bases for your review of the SRVloads in the Mark I Containment Long Term Program. We will conduct a plant specific evaluation of the FitzPatrick torus structures based on the results given in the Final Load Definition Report for the Long Term Program. We expect to provide the results of this evaluation to you -
for your review as soon as they can be completed. Based on the above, it is the Authority's position that a commitment for parformance of the analysis requested in your letter of December 9,1977 is not currently justified.
Very truly yours, Wilbur L. Gronberg Assistant General Manager-Engineering Atts.
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ATTACHMENT A Power Authority of the State of Naw York License No. DPR-59 Dookat No. 50-333 Saptambar, 1978 e
EVENT 1* - STUCK-0 PEN REIIEF VALVE FROM POWER OPERATION Initial Conditions 1.
Operation at Licensing Bases safety analysis limit steam flow conditions.
(JAFNPP = 105% NBR steam flow).
2.
Maximum RHR heat exchanger service water temperature.
(JAFNPP = 77'F).
3.
Suppression pool temperature at normal power operation Technical Specification limit (Tgp).
(JAFNPP = 95 F.)
4.
Minimum Tech Spec suppression pool water volume.
(JAFNPP = 105,600 cu. ft.)
5.
Drywell air pressure (JAFNPP = 1.7 psig) 6.
Drywell air temperature (JAFNPP = 135 F)
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7.
' Torus. air pressure (JAFNPP :-0.1 psig) 8.
Recirculation pumps operating.
Event Sequence E3 nt Description Time Temp
- t = 0.0 T
Pool temperature alarm at initial a
op Condition 3.
Initiate actions to turn RHR loop (s)* on for pool cooling.
SRV fails open.
t + 3 minutes **
RHR loop (s)* on for pool cooling and torus spray.
a t
T Reactor Scram ***
s s
(T = 110 F. for JAFNPP) s t + 10.5 seconds Isolation (assuming automatic isolation on S
Lo-Lo water level).
t + 10 minutes ##
2-3 additional SRV's manually actuated (as a
necessary) to depressurize the reactor.
- t T
Drywell high pressure trip (JAFNPP = 2.7 psig).
b
b RilR automatically switched out of pool cooling mode.
Time t, t, and the number of SRV's to be manually actuated bytheopehatortobedeterminedbyanalysis.
s Corresponds to nonproprietary Question 1(a) if two RHR loops available and to 1(b) if one RilR loop available.
U4Z: csc/16Il
footnotes - EVENT 1 - (continued)
The operator can complete the actions necessary to, turn the RHR,...._..
loop (s) un within three minutes.
Manual scram.
"^^
i The bulk suppression pool temperature is assumed to be 95*F when an SRV inadvertently fails open.
This is the maximum pool temperature allowed during normal power operation (Technical Specifications Section 3.7.A.1).
Also Section 3.7.A.1 in the JAFNPP tech specs specifies that the reactor shall be scrarr.med f rom any operating condition when the suppression pool temperature reaches 110'F.
The operator can determine which valve is stuck open within ten minutes.
- lhe operator can prevent the drywell pressure from reaching 2.7 psig by using the torus spray.
Therefore, a drywell high pressure trip is considered unlikely.
However, if it did occur, th<s opeiator would vont the drywell to the Standby Gas T.reatment System 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the trip.
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i LMZ:csc/1612
Assumptions, For Event 1 1.
Maximum operatino condensate storage water temperature. (T = 850F) 2.
Normal automatic operation of HPCI, RCIC - but manually controlled thereafter.
3.* Single RHR loop available for pool cooling.
4.
Vessel liquid mass adjusted to account for subcooled liquid in the RPV and piping.
5.
Metal mass adjusted to account for lower temperature of some metal components.
6.
Effect of team void collapse included.
s 7.
Outy of RHR heat exchangers based on 40 years of crud.
8.
CR0 flow maintained constant.
9.
SRV capacities at 122.5% of ASME rated.
10.
Licensed docay heat curve for containment analysis (adjusted to account for celay betwaen scram and isolation).
11.
On plants with turbine-feedwater pumps (JAfNPP), the feedwater flow coastdown begins 7 seconds after containment isolation.
12.
Event terminates in cold shutdown.
i For nor. proprietary Question 1(a), both RHR loops are assumed operational.
Lf1Z:csc/1613
EVENT 28 STUCK-OPEN RELIEF VALVE FROM ISOLATED HOT STANDBY Initial tonditions 1.
Operation at Licensing Bases safety analysis limit steam flow conditions before isolation.
(JAFNPP = 105% NBR steam flow).
2.
Maximum RHR heat exchanger service water temperature.
(JAFNPP = 77'F.)
3.
Suppres'sion pool temperature at normal power operation Technical Specification limit (Tgp).
(JAFNPP = 95 F.)
4 Minimum Technical Specification suppression pool water volume (JAFNPP = 105,600 cu. ft.)
o 5.
Drysell air pressure (JAFNPP = 1.7 psig.)'
6.
Drywell air temperature (JAFNPP = 135 F.)
7.
Torus ~ air pressure (JAPNPP =-0.1 psig.)
8.
Recirculation pumps operating.
9.
Reactor pressure when isolated is 920 psig.
i Event Sequence lime (Min.)
Event Description
- t
=t
= 0.0 An abnormal operational transient has occurred, which a
s resulted in reactor scram and isolation.
The suppression operatorinitiatesac& Son (InitialCondition3).
The pool temperature is T s to turn RHR loop on for pool cooling.
't
+ 3 minutes *
- RHR loop on for pool cooling.and torus spray.
a 0<t<30 Reactor pressure maintained using SRV.
t Single SRV sticks open at 120 F.
Operator begins reactor pressure vessel depressurization if required o
by opening additional SRV's.
- t Urywell high pressure trip (JAFNPP = 2.7 psig).
'b automatically switched out of pool cooling mode, l.ie number of SRV's to be manually actuated by the operator to be determined by the analysis.
LMZ: csc/1614
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. Footnotes - EVENT 2 (Co'ntinued)
Corresponds to nonproprietary Question 1(c).
This event does not conform to the plant licensing basis because it requires a transient plus a single failure. Therefore, this event should not be analyzed.
The bulk suppression prol temperature is assumed to be 95*F rather than 120 F when the reactor is scrammed.
This is the maximum pool temperature allowed before pool cooling would begin.
Also, Section 3.7.A.1 in the JAFNPP tech specs specifies that the reactor shall be scrammed from any operating condition when the suppression pool temperature reaches 110df.
The operator can complete the actions necessary to turn the RHR loop (s) on within three minutes Section 3.7. A.l.C.4 in the toch specs specifies that during reactor isolation conditions, the reactor pressure vessel shall be depressur-ired to less than 200 psig at normal cooldown rates if the pool temperature reaches 120 F.
The operatnr can prevent the drywell pressure from reaching 2.7 psig by using the torus spray.
Therefore, a drywell high pressure trip is considered unlikely.
However, if it did occur, the operator would vent the drywell to the Standby Gas Treatment System 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the trip.
LMZ:csc/1615
Assumptions For Event 2 1.
Maximum operating condensate storage water temperature. (T = 850F) 2.
Normal automatic operation of HPCI, RCIC - but manually controlled thereafter.
3.
Single RHR loop available for pool cooling.
4.
Vessel liquid mass adjusted to account for subcooled liquid in the RPV and piping.
5.
Metal mass adjusted to account for lower temperature of some metal components.
6.
Effect of steam void collapse included.
7.
Outy of RHR heat exchangers based on 40 years of crud.
8.
CRD flow maintained constant.
9.
SRV capacities at 122.5% of ASME rated.
10.
Licensed decay heat curve for containment analysis (adjusted to account for delay between scram and isolation).
11.
On plants with turbine-driven feedwater pumps (JAFNPP), feedwater flow coastdown begins at 7 seconds after containment isolation.
12.
Event terminates in cold shutdown.
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LMZ:csc/1616
EVENT 3*
SMALL BREAK ACCIDENT WITH ADS Initial Conditions 1
Operation at Licensing Bases safety analysis limit steam flow c9nditions. (JAINPP = 105% NBR steamflow).
2.
Maximum RHR heat exchanger service water temperature.
(JAFNPP = 77'F.)
3.
Suppression pool temperature at normal power operation Technical Specification limit (Tgp).
(JAFNPP = 95*F.)
4.
Minimum Technical Specification suppression pool water volume.
(JAFNPP = 105,600 cu. ft.)
5.
Recirculation pumps operating.
Event _ Sequence Time ~(Min.),
Event Description
- 0. 0 SBA occurs during normal plant operation **
ADS blows down.the plant No operator actions assumed, event runs to completion.-
The suppression pool temperature versus discharge mass flux.is determined by the analysis.
s k-Corresponds to nonproprietary Question 1(d).
The bulk suppression pool temperature is assumed to be 95 F rather than 120 F when the SBA occurs.
Also, section 3.7.A.1 specifies that the reactor shall be scrammed from any operating condition-when the suppression pool temperature reaches 110 F.
LMZ:csc/1617
Assumptinjs For Event 3 0
1.
Maximum operating condensate storage water temperature. (T = 85 F) 2.
Since ADS operates, HPCI failure is assumed.
No credit taken for RCIC.
3.
Both RiiR loops available for pool cooling.
4.
Vessel liquid mass adjusted to account for subcooled liquid in the RPV and piping.
5.
Metal mass adjusted to account for lower temperature of some metal components.
6.
Effect of steam void collapse included.
7.
Duty of RHR heat exchangers based on 40 years of crud.
8.
SRV capacities at 122.5% of ASME rated.
9.
Licensed decay heat curve for containment analysis (adjusted to account for delay between scram and isolation).
10.
On plaats with turbine-driven feedwater pumps (JAFNPP), the feedwater flow coastdown begins at 7 seconds after containment isolation.
11.
Event terminates in cold shutdown.
12.
LPCI mode of RHR, LPCS, and A05 available.
13.
Limiting (Peak Cladding Temperature) small line break.
14.
One ADS valve out of service as allowed in Technical Specifications.
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LMZ:;sc/1618
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o EVENT 4* ISOLATI0ffAND REACTOR fi' PRESSURIZATION Initial Conditions 1
4 s
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1.
Operation at Licensing Bases safety analysis limit steam flow conditions.
(JAFuPP = 10%% NBR steam flow).
2.
Maximum RHR heat exchanger service water temperature.
(JAFNPP = 77'F) 4 3.
Suppression pool tImperature at normal power operation Technical Specification. limit (Tgp):
(.1AFNPP = 95 F.)
4.
MidmumTechnicalSpecificatjonsuppressionpoolwatervolume.
(JAFNPP = 105,600 cu. ft.)
.5.
.Dryseie air pressure,.
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(JAfNPP = l'.7 psig.)
6.
Drywell aie temperature,
(.1AFNPP = 135 F.)
7.
TON,' a i r pi es sure.
(JAFNPP = -0.1 psig.)
8.
Recirculation pumps operating.
Event Sequence Time (Min.)-
Event Description
- t
=t
= 0.0 Pool temperature alarm.
Reactor isolation and scram a
s (Initial Condition 3).
Initiate actions to turn RHR lonps on for pool cooling.
(
t, + 3 minutes **
Both RHR loops on for pool cooling and torus spray.
Reactor pressure maintained using SRV (intermittent 0<t<tc operation).
Initiate cooldown at < 100 F/hr.*# using SRV's at t
c 120 F.***
k Orywell high pressure trip (JAFNPP = 2.7 psig).
- t'b automatically switched out of pool cooling mode.
W lime t', t, and the number of SRV's to be manually actuat6dbhtheoperatortobedeterminedbyanalysis.
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LMZ:csc/1619 s
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o Footnotes to Event 4 - Isolation and Reactor Depressurization (Cont'd)
Corresponds to nonproprietary Question 1(e).
The operator can complete the actions necessary to turn the RHR
^
loop (s) on within three minutes.
However, this time is not critical, due to the low heat removal capacity of the RHR heat exchangers.
If only one RHR loop is available cooldown rate is not limited to 100 F/hr.
Section 3.7.A.I.c.4 in the tech specs specifies that during reactor isolation conditiuns, the reactor pressure vessel shall be depres-surized to less than 200 psig at normal cooldown rates if the pool temperature reaches 120"F.
The bulk suppression pool temperature is assumed to be 95 F rather than 120"F.
This is the maximum pool temperature allowed before
(
pool cooling would begin.
Also, Section 3.7.A.1 in the JAFNPP tech specs specifies that the reactor shall be scrammed from any operat-ing condition when the suppression poo-1 temperature reaches 110'F.
The operator can prevent the drywell pressure from reaching 2.7 psig by using the torus spray.
Therefore, a drywell high pressure trip is considered unlikely.
However, if it did occur, the operator would vent the drywell to the Standby Gas Treatment System 2 to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the trip.
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LMZ:csc/16110
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O Assumptio~s For Event 4 1.
Maximum operating condensate storage water temperature. ('r = 85 F) 2.
Normal automatic operation of HPCI, RCIC - but manually controlled thereafter.
3.
Both RHR loops available for pool cooling.
4.
Vessel liquid mass adjusted to account for subcooled liquid in the RPV and piping.
5.
Metal mass adjusted to account for lower temperature of some metal components.
6.
Effect of steam void collepse included.
7.
Duty of RHR heat exchangers based on 40 years of crud.
8.
CRD flow maintained constant.
9.
SRV capacities at 122:5% of ASME rated.
10.
Licensed decay heat curve for containment analysis (adjusted to account for delay between scram and isolation).
11.
On plants with turbine-feedwater pumps (JAFNPP), the feedwater flow cuastdown begins at 7 seconds after containment isolation.
12.
Event terminates in cold shutdown.
s 9
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LMZ:csc/16111 i
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l ATTACHMENT B 1
2 Power Authority of the State of New York License No. DPR-59 Docket No. 50-333 Saptember,1978 e
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4 SUPPRESSION POOL TEMPERATURE MONITORING SYSTEM The suppression pool temperature monitoring system consists of four (4) instrument loops (channels). Two of the instrument loops each contain a temperature element, temperature transmitter, and a temperature indicator which provide indication in the control room. The two remaining instrument loops each contain a temperature element, temperature transmitter, and feed seperate temperature recorders located in the relay room (auxiliary control room). All four loops provide inputs to the process computer. hiake, locationi range, and accuracy of these instruments are listed in Figure 1.
Figure 2 shows the relative location of the temperature elements to the safety relief valve discharge points. The two temperature element pairs are located approximately 90 apart. The safety relief valve discharge 0
points are spaced throughout the suppression pool.
FIGURE I INSTRUhfENT htAKE RANGE ACC.
LOCATION 27-RTD-101A-D Taylor 0-600 F
+.1F Torus (See Fig. 2) 0 27-TT-101A-D Taylor 50-3500 F
+.35's SIP (Relay Room) 27-T1-101A-B Taylor 50-3500F
+3F 09-75 (Control Room) 27-TR-102, 103 Kaye 50-3500 F
+. 3*.
SIP (Relay Room COSIP.
INSTRUMENT POINT ID #
i 27-RDT-101 A F1020 B
bl021 C
F1022 D
F1023
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SRV & TE LOCATIONS FOR SUPPRESSION RAMS POOL TEMPERATURE MONITORING SYSTEM
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