ML20091A575
| ML20091A575 | |
| Person / Time | |
|---|---|
| Site: | Monticello |
| Issue date: | 10/31/1977 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9105160389 | |
| Download: ML20091A575 (20) | |
Text
.
NSMMAT0'lY 003'.E 5 C01Y NOMTHENN 8TATES PoWEM C0MPANY
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Mr Victor Stello e' ;
Division of Operating Reactors
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&,4 IS//,, y U S Nuclear Regulatory Ccunission 0
Washington, DC 20555 g
Dear Mr Stellot 4,
,g FDNTICEllh NUCIZAR GENERATING p1 ANT Docket No. 263 License No. DPR-22 Documentation of Basis for Continued Operation Sequential SRV Actuations of Isolation Events At the request of the NRC Staff, the Mark I Owners Group and General Electric rep-resentatives met with the NRC Staff October 27, 1977 to discusa potential influence on Mark I con',ainments of SRV sequential actuations associated with isolation events.
In that meeting General Electric presented a preliminary evaluation using most probable loads basis and short tem program acceptance critoria for all operating plants.
At the conclusion of the October 27 meeting, Staff requested documentation of the basis for continued operation and requested consideration of ccanitinents to operational procedures to reduce the probable incidence of SRV multiple-valve sequential actuations, said documentation to be sulnaitted by November 1,1977.
Further, NRC Staff indicated an intent to fomally request that a plant-unique assessment be provided witSin 60 to 90 days, with such assessment to be based on the conservative General Electric dynamic model prediction of sequential r.n:1tiple-valve actuations, application of conservative factors for correlation of cultiple and consecutive valve actuation effects, and use of the short tem program acceptance criteria.
This submittal is believed to provide all of the requested information, including that which Staff indicated may be required within 60 to 90 days.
'Ihe Monticello plant has eight safety relief valves with all setpoints at approxi-nately 1068 psig. All valves arc by Target Rock.
Each SRV discharge line has a recorded tenperature monitor, a pressure switch monitor, a tvo inch vacuum breaker valve, and an eight inch vacuum breaker valve. All vacuum breaker setpoints are adjusted to be equal to or less than 0.2 psi. The pressure switch monitor set-points are approximately 5 psig and provide input to the plant computer sequence-of-events monitor for specific discrimination of SRV actuations and closures.
9105160309 771031 PDR ADOCK 05000263 P
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1 NORT)
FtN OTATECO POWEER COM, 4NY Mr Victor Stello page 2 October 31, 1977 Hont icello plant -l'nique Trannient Analysis The purpose of using the transient analysis mcdel was t o predict the namber of SRV's which might participate in multiple valve consecutive actuations for Monticello isolation events.
The results of this analysis indicate that all eight SRV's will open and close in perfect unison for all initial and subsequent actuations, in-dependent of the magnitude of demand for over-pressure relief capacity generated by the cass-energy transient of the isolation event.
In the Monticello case this is n(ither a prediction nor an analysis result.
It is the consequence of model assumptions that valves of like nominal setpoint, specification and manuf acture will perform with exactly identical characteristics for every actuation of every valve.
Qualification testing of Target Rock valves have demonstrated significant variations, within the limits of specified performance, for pilot actuation delay time and ma i n di s c s t r oke t ime.
Because of the variability of and relation between these two characteristics, it is quite possible for the transient pressure to exceed the ef fective setpoint of all valves and have the pressure reduced holow this level by the first-to-open valve, with no other valves actually actuating.
Two i s oi nt i en events from full rated power have occurred at Monticello.
In both cases only a single valve opened f or even the initial actuation when all valves were adjusted to the same nominal setpoint.
From this experience we must conclude that singic valve actuation is the typical characteristic, and that the all-valves, t.mitiple actuation, resulting fran the model assumptions is the remotely prebable event.
Attachment C provides a summary of four isolation ev(nts which have occurred at Monticello since initial operation.
For your underst anding. Attachment C also includes a summary of relevant design changes and procedure changes since initial operation.
Although the transient analysis model grossly over-predicts consecutive multiple-valve actuation of all eight SRV's, compared to experience of single valve actuation, the eight valve consecutive actuation is used for purposes of con-servatism as requested by the NRC Staff.
Justification for Continued Operat_ip1 Attachment "A" provides the basis for justification of continued operation of the Monticello plant in light of the potential influence of sequential multiple valve actuations.
This is essentially the preliminary assessment for Monticello as presented by General Electric in the October 27, 1977 meeting with NRC Staf f.
This assessment in our opinion is reasonabic and conservative, and concludes that STP criteria is more than satisfied with limiting strength ratios of.24 for eight valve consecutive actuation.
This assessment is especially conservative in light of actuni operating experience that single valve actuation is typical of isolation f rom rated power.
NORTI
.RN OTATED POWER COM. ANY 4
Mr Victor Stello page 3 October 31, 1977 lio f urther procedure changes are contemplated in light of procedures in ef fect since July 25, 1971 and as further revised January 6, 1977.
plant-Unique Asses ment end Action plan in the October 27, 1977 meeting with liRC Staf f, Staff indicated a requirement for plant-unique assessment using multiple-valve consecutive actuations as predicted by the General Electric transient analysis nodel and tuore conservative correlations for multiple valves and consecutive actuations.
The 11Sp assessment for Monticello on the request basis is presented in Att achment "B" with the sternary and c(uparison to the General Electric preliminary assessment shwn on the attachment "Sutinary".
Again, we conclude that the assuttption of an 8 SRV multiple consecutive actuation ir, cowrvative in the extreme in light of operating experience that a single SRV is typical for even the initial actuation for a rated pcuer isolation event.
The une of arithmetic sum of participation f actors is conservative for evaluation of support structure loads because it assumes that both structural response and applied loads combine linearly in ccanposite.
The use of peak stress of all runs and Sl<SS ccinbination of participation f actors is in itself a conservative method of evaluating shell stress; this is illustrated by the ciretanstance that the same approach bounds the three-valve test results where direct load participation might be expected to be more d(uninant than response participation.
Since fcr the extreme assumption of 8 valve sequential actuation all elements of the structure are well within STp acceptance criteria and also within a few per-cent of code allcvable stresses, no structural tuodifications or procedure changes are warranted at this time.
Yours very t ruly, he YW
/
L 0 Mayer, pE Manager of lioclear Support Services IDM/Gml/ak cet J G Ecppler G Charnoff MPCA - Attn: J W Teman
I I
i UNITED STATES NUCLEAR RECULATORY COMMISh10N NORTilERN STATES POWER COMPANY HONTICELLO NUCLEAR CENERATING PIANT Docket No. 50 263 License No. DPR-22 l
l LETTER DATED 0ctober 31, 1977 RESPONDING TO NRC REQUESTS FOR INPORMATION ON CONTA1104ENT DESIGN Northern States Power Company, a Minnesota corporation, by this letter.
dated October 31, 1977 hereby sulaults infonnation in response to NRC i
requests for infonaation concerning the Mark 1 Contaitunent.
4 This request contains no restricted or other defense infonnation.
NORTHERN STATES POWER COMPANY t
N Id>
By J Wachter Vice President, Power Production
& System Operation on this 31st day of October, 1977
, before me a notary public in and for said County, personally appeared L J Wachter, Vice President, Power Production and System Operation, and being first duly sworn acknowledged that he is authortred to execute this document on behaH of Northern States Power Company, that he known the contents thereof and that to the best of his knowledge, infonnation and belief, the statements made in it are true and that it is not interposed for delay.
/WM I
McWioM
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Attachment "C" Page 1 of 3 1.
The Monticello Plant initially had four safety relief valves dis-charging to the torus and four conventional safety valves.
SRV discharge lines terminated in the suppression pool as vertical straight pipe near the torus wall with no discharge device.
2.
July 25,1971-Operating procedures were issued to require operator to take manual control of SRV following isolation and blow down to 950 psig, with pressure to be maintained between 1000 and 950 psig by manual blowdown as necessary.
3.
January,1972-SRV discharge lines were extended to torus center line and rams head discharge devices installed.
4 July 25,1972-Installed SRV discharge pressure switches with 5 psig setpoints and inputs to computer sequence of events monitor.
5.
April,1974-Replaced the four conventional safety valves with four SRV's.
SRV discharge line ad31tions installed with rams heads and pressure switch monitors.
6.
Jatuary 6,1977-Operating procedures revised to require operator to take manus 1 control of SRV following isolation and blowdown to 800 psig. Pressure to be maintained between 1000 and 800 psig by manual blowdown as necessary.
Specified sequence of blowdown so all SRV's would be actuated once before re-activating first SRV.
(Sequence of SRV lifts based on history cf SRV actuations, i.e.,
1st valve specified for torus bay previously experiencing fewest ac tua tions. )
7.
October 1977-Added 8-inch vacuum breakers to all SRV discharge lines.
Installed three prototype SRV discharge "T-Quenchers".
EVENT #1 Date: thy 20, 1971 Power Level:
75%
Initiating Event:
Startup test STP 11, Initiated by tripping ROIS relays with opening of test switch.
Sequence of Events:
1.
MSIV closure at 1318.
2.
Rx pressure peaks at 1069 psig, approximately six seconds af ter initiation.
3.
No automatic lift on initial pressure peak.
4.
"D" safety relief valve manually operated to reduce Rx pressure. Actual nmaber of manual lif ts cannot be determined but only one is suspected.
l l
Attachment "C" Page 2 of 3 EVENT #2 Date: May 24,1971 Power Levels 100%
Initiating Event:
Oscillations in the steam line flow signal had initiated the high steam flow isolation of Group I.
Sequence of Events:
1.
MSIV closure at 2146.
2.
Auto lif t of "D" safety relief valve (1085 Rx pressure peak) 3.
Rx pressure reduced to 976 psig.
4.
Manual lif t of "D" safety relief valve at 1035 psig approximately 4 minutes after initial lift.
5.
Rx pressure reduced to 995 psig.
6.
MSIV's opened.
EVENT #3 Date:
July 14, 1971 Power Level:
91%
Initiating Event:
Pressure transmitter was valved in service following routine calibration, a pressure surge occurred in the instrument sensing line.
The surge tripped the main steam line high flow switches connected to the same line causing a group I isolation.
Sequence of Events:
1.
MSIV closure at 1348.
2 SRV opens Rx press 1060 psig peak.
3.
Rx press drops to 995 psig.
4.
SRV opens Rx press 1090 psig peak, 1352*.
5.
Rx press drops to 1025.
6.
SRV opens Rx press 1095 psig peak, 1353*,
7.
Rx press drops to 1015.
8.
SRV opens Rx press 1095 psig peak, 1355*.
9.
Rx press drops to 1040 psig.
10.
SRV opens Rx press 1090 psig peak, 1357*.
11.
Rx press drops to 1035 psig.
12.
SRV opens Rx press 1090 psig peak,.%s1358*,
13.
Rx press drops to 1030 psig.
14.
SRV opens Rx press peak 1090 ps.g,ms1359*.
15.
Rx press drops to 1030 psig.
16.
SRV opens Rx press peak 1092 psig,es1401*.
17.
Rx press drops to 1025 psig.
18.
SRV opens Rx press peak 1095 psig,.g/1402*.
19.
Rx press drops to 1018 psig.
- Estbnates made from measuring Rx press chart.
l NOTE:
It appears that the Icast the "A", "B" and "C" l
valves lifted during this event based on discharge pipe tem;.erature recorder indications. We cannot l
tell which one lif ted at a given time from the t
available information.
l
Attachment "C" Page 3 of 3 EVENT #4 Date: Novanber 6,1973 Power Level: 99.5%
Initiating Event:
Inadvertant trip of a main steam line high flow sensor during routine instrument surveillance resulted in a Group 1 isolation.
Sequence of Events:
1.
HSIV closure at 1338:47.62.
2.
Rx pressure peaks at 1065.
3.
"C" safety relief valve auto opens at 1338:51.82.
4.
"C" SRV closes at 1339:11.03 at Rx press, of 970.
5.
"D" SRV manually opened at 1341:08.47, Rx press 1035.
6.
"D" SRV closed at 1341:20.46 Rx press 975.
7.
"D" SRV manually opened at 1341:43.&4, Rx pressaJ1024.
8.
"D" SRV closed at 1341:56.16 Rx pressnJ970.
9.
"D" SRV manually opened at 1342:20.48 Rx pressnJ1024.
10.
"D" SRV closed at 1342:33.73, Rx pressr%#966.
11.
"D" SRV manually opened at 1343:13.41, Rx pressrV1024.
12.
"D" SRV closed at 1343:25.75, Rx presse%#966.
13.
"D" SRV manually opened at 1344:24.10, Rx presseJ1028.
14.
"D" SRV closed at 1344.37.70, Rx pressv%#964.
15.
"D" SRV manually opened at 1345:38.69, Rx pressed 1028.
16.
"D" SRV closed at 1345:51.52, Rx p re s s es> 965.
17.
"D" SRV manually opened at 1347:10.93, Rx pressrJ1043.
18.
"D" SRV closed at 1347:27.54, Rx press #%J910.
NOTE: These lift times are accurate tLmes as indicated by the sequence of events recorder.
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Minneapolis, Minnesota 55401
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Notori ze d 10/31/77......
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