ML20003G222

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Forwards Info Re Reactor Bldg Purge Valves in Response to TMI Action Plan Item II.E.4.2.6 in NUREG-0737
ML20003G222
Person / Time
Site: Rancho Seco
Issue date: 04/20/1981
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Stolz J
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.4.2, TASK-TM NUDOCS 8104280488
Download: ML20003G222 (15)


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esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 s street. Box 15830. sacramento, California 95813; (916) 452-3211 April 20, 1981 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION JOHN F STOLZ CHIEF OPERATING REACTORS BRANCH 4 US NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION, UNIT NO. 1 REACTOR SUILDING PURGE VALVES TMI ACTION PLAN ITEM II.E.4.2.6 Your letter of October 23, 1979 requested the Sacramento Municipal Utility District to comit to operate the reactor building purge system in accordance with your interim position on operation of this system. This matter is also the subject of item II.E.4.2.6 in NUREG-0737.

In letters dated December i3, 1979 and January 18, 1980 the District comitted to limit purging to times the reactor is at cold shutdcwn or refueling shutdown, pending resolution of purge valve operability qualification.

The District has performed aa analysis which provides assurance that purge valves will operate when positioned at or less than 80% of full stroke for the motor acerated valves inside the containment,and 60% of full stroke for the air ocera-ted valves outside the containment. With this assurance, we are confident that the FSAR analysis for a loss of coolant accident during a purge is valid and that operation of the purge system during reactor operation does not involve an unreviewed safety question. The safety analysis is attached for your infomation.

In addition to the above concern, it has been deten.dned that the failure mode of the solenoid ocerated valves, providing air to the air operated purge and pressure equalizing valves, is in the open direction, resulting in these valves opening, should a loss of DC power occur. Although this power is not the motive power to the valve, the District has comitted by letter dated November 19, 1980 to operate with the purge valves closed, and air isolated, until the failure mode can be reversed. The refueling outage we are now completing, occurred earlier 4 c rrj'y n s

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than scheduled due to inspection requirements on the main turbine, and parts-were unavailable to make this radification. For that reason, we comit to continue plant operation with the purge-valves closed, and air isolated, until these modifications can be made. Once these modifications are made, i

the District does intend to resume purging during plant operation.

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g ohn Mattimoe Assistant General Manager and Chief Engineer Enclosure 1

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REVIEW 0.

PROPOSED 50.59 FACILfTV Ch..4GE Log Ho. 189 & 190 1.

CESCRIFTION:

This mcdification limits the position of tne reactor building purge valves such, tnat allowable stresses will not be exceeded and adequate closure torques will be available.

NCR S1911 & S1912 ECN J-SdJo N 2.

SAFETY ANALYSIS: In response to an NRC letter, dated October 23, 1979, the District cor:nitted in letters, dated December 13, 1979 and January 18, 1980, to limit the purging to times the reactor is at cold shutdown or :efueling shutdown, pending resolution of purge valve operability qualification. The attached design basis report provides assurance that the purge valves will operate when positioned at or less than the specified ocening.

With this assurance, the FSAR analysis for a loss of coolant accident during a purge is valid, and this modification does not involve an unreviewed safety question. As d'scussed in the minutes to PRC meeting No. 816, dated September 30, 1980, Generation Engineering will prepare an informational letter to the NRC based on the findings from the review

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/fUlf0 Licensing Engineer Date Mariager Generation E g1neering Jate 3.

PRC RECCMMENDATION: 50.59(a)

Yes O No g 50.59(b)

Yes % No C DZSPOSITION OF PRC:

Unanimously reccmmends proposal 3 d.

Safety analysis inadequate O

a.

b.

Send to MSRC for concurrent.a g

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MSRC review prior to implementing O c.

Recorrends not to proceed C

f. gTes go }syytem, required E

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PRO Chairman f

Date 4

ANALYSIS: 50.59(a)

Yes O Recommend t'o Proceed

'Yes O No %

uired[

No p Refer to MSRC 50.50(b)

Yes Test of system r U

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//-/O 4-0 Plant Sucerintencent Date 5,

MSRC FINDINGS: 50.59(a)

Yes C No R 50.59(b)

Yes E No O DlSPOSITION CF MSRC:

a.

Recommends proposal 8

c.

Recomends not to proceed O Safety aglysis inadecuate O 12 fI9l80 b.

Send to NRC for approval O d.

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$ttdh a MSRC Ce irmat d

Date 6.

COMMISSION APPROVAL OBTAINED Date MSRC Chairman i

7.

RETEST COMPLETE AND ACCEPTABLE: Test results approved Supervisor Engineering and Quality Control S.

OVERALL REVIEW: Plant modification change complete.

Manager Nuclear Operations Date 9.

DOCL' MENTATION COMPLETE:

Quality Assurance 01 rector Date suuomes seso

Log No. 189 & 190 SAFETY ANALYSIS FORMAT RANCHO SECO NUCLEAR GENERATING STATION trNIT NO.1 ECN NCR S1911 & S1912 Work Request DESCRIPTION:

This mcdification limits the position of the reactor building purge valves such, that allowable stresses will not be exceeded and adequate closure torques will be available.

REASON FOR CHANGE:

This modification will allow the react; building purge valves to be partially opened during plant operation.

EVALUATION AND 3 ASIS FOR THE SAFETY FINDINGS:

In response to an NRC letter, dated October 23, 1979, the District cemitted in letters, dated December 13, 1979 and Janucry 18, 1980, to limit the purging to times the reactor is at cold shutdown or refueling shutdown, pending-resolutien of purge valve operability qualification. The attached design basis report provides assurance that the purge valves will cperate when positioned at or less than the specified opening. With this assurance, the FSAR analysis for a loss of coolant accident during a purge is va!id, and this modification does not involve an unreviewed safety question.

As discussed in the minutes to PRC meeting No. 816, dated September 30, 1980, Generation Engineering wi 4 va-pare an informational letter to the NRC, based on the findings from the review of this safety analysis.

iMThe proposed change will not increase the probability of occurrence or the

" consequences of an accident or malfunction of equiprent irrportant to safety previously evaluated in the FSAR or create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR or reduce the margin of safety as defined in the basis for any Technical Specification.

SAFETY FINDING:

The proposed change does not involve a change in tha Technical Specifications or an unresolved safety question.

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DESIGN BASIS REPORT NCR S-1911 and S-1912 1.

PURPOSE OF DESIGN CHANGE:

Limit the position of the reactor building purge valves such that allowable stress will not be exceeded and adecuate closure torque is available.

SFV 53504

<80' SFV 53605' 780*

SFV 53503 760*

SFV 53604 560*

II.

DESIGN CRITERIA USED:

Reactor Building Pressure for 14.1 Ft.

LOCA.

1)

Allis-Chalmers Report A-C, VER 0209, da.ted 12/17/79.

2)

Test Report on an Allis-Chalmers 6" STREAMSEAL Butterfly Valve.

Valves close within 3.5 seconds (Air / Spring and 5 seconds 3)

(Motoe Operated).

4)

Initial delay time of b.5 seconds.

Maximum allowabla shaf e torque 13,300 f c. lbs. (AWA).

5) 6)

Maximum allowable operator torque 41,600 ft. lbs. (motor operated valve).

Allis-Chalmers Letters:

7)

Theodore Kopey to L. Smith, January 9,198C.

8)

Theodore Kopcy to D. Blachly, February 6, 1980.

9) ituadore Kopey to D. Blachly, March 23,1980.

10)

P.R. Schwartz to Atten. D. Blachly, April 14, 1980.

SMUD Letters:

11)

R. J. Rodriguez to Mr. LaSage, December 28, 1979.

12)

D. C. Blachly to Theodore Kopey, March 13, 1980.

III. CALCULATIONS AND DESIGN INFORMATION (reference 2) concluded that accurate cal-Allis-Chalmers test report culation of torque may be made using the data, and formulas given within the test report.

The total shaft torque is calculated by algebraic addition of disc dynamic torque and bearing torque. The dynamic torque is given by:

Td" T*

T = Dynamic Torque.

d G = Experimentally determined torque coefficient.

T D = Diameter of valve disc.

aP = Experimentally determined pressure dif ferential across the valve.

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D = Diameter of valve disc (f t) d = Shaft diameter (in) f = Friction Coefficient (.12) 3P = Experimentally determined pressure drop across the valve'.

Test report VER 0209 contains the data for torque coeffi 'ent and pressure drop for various opening positions and inlet pressures of given disc thick-ness ratios and inlet configuration Linear interpolation between pressures is assumed.

The inlet configuration for SFV 53504 is with-an elbow at 90* to the valve shaf t and the curved f ace of the disc upstream.

This is considered most limiting configuration (test #27).

The inlet configuration for SFV 53605 is with an elbow inline with the valve shaft (test #26). The configuration of SFV 53604 and SFV 53503 is flat face upstream (test 128). Closure Reactor Building pressure initiation is assumed at 0.5 seconds from rupture.

is a maximum of 7 psig. This is conservative since initiation actually occurs at a building pressure of 4 psig.

Reactor Buildius pressure vs. time is shown in my March 13, 1980 letter to Theodore Kopey in tabular form in Table Two (2), and graphically as an The limiting reactor building pressure is the maximum pressure attachment.

This curve was based on the ramp curve shown in figure 14.4-5 of the FSAR. Motor operated valve closure is assume spectrum curves referenced above.

to vary-linearly with respect to time (0*/sec) during the LOCA condition.

Air /. Spring operated valves is assumed to vary linearly with respect to crosshead travel ("/sec) from the full closure times are based on experim-ental data open position with no differential pressure across the valve.

Maintaining greater than the required torque will not significantly change these times under the dynamic conditions.

IV.

FAILURE MODE The failure modes analyzed in the original FSAR are unchanged by this repair.

V.

CONCLUSIONS and SFV53605 - Motor Operated Valves:

SFV535004 By limiting the valves full open position to 80* open, the maximum calculated torque is 12009 ft-lbs.

This is below the recommended j

13300 ft-lbs. recommended by the AWWA. This corresponds to a com-bined stress of 10418 psi, well below the ASME VIII allowable of l

16000. Available torque is 41,600 ft-lbs.

SFv53503 and SFV53604 - Air / Spring Operated Valves:

(

By limiting the valves full open position to 60* open, the maximum calculated torque is 7700 ft-lbs. The combined stress is 12261 psi, well below ASM VIII allowable of 16000 psi.

The minimum difference Attachment between available and allowable torque is 4500 ft-lbs..

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