ML20052D275

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Advises of 820129 Facility Shutdown for Containment Purging to Decrease Radioactivity & Atmospheric Temp.Engineering Change Notice & Related Info Encl
ML20052D275
Person / Time
Site: Rancho Seco
Issue date: 04/28/1982
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Stolz J
Office of Nuclear Reactor Regulation
References
NUDOCS 8205060428
Download: ML20052D275 (13)
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Text

{{#Wiki_filter:1 d= $SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 5201 S Street, Box 15830, Sacramento, California 95813; (916) 452-3211 January 28, 1982 xm ild /' DIRECTOR OF NUCLEAR REACTOR REGULATION d'[ ~ ~\\ /'g/ \\L ATTH: JOHN F STOLZ, CHIEF OPERATING REACTORS, BRANCH 4 H. U S NUCLEAR REGULATORY COMMISSION 7 ^l' ,#'+,., sy HASHINGTON DC 20555 M '4 -b ;7 ~ ~lll l} v.s s v V'Na#}/ y - ? DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT 1 CONTAINMENT PURGING REASON: Rancho Seco Unit I has been operating at essentially full power since Decen ber 1981. The Technical Specifications, Section 3.12, " Shock Suppressors", require a snubber inspection durino the early part of February. To be on the conservative side of this license requirement, SMUD plans to shutdown Rancho Seco at midnight, January 29, 1982. WHY: The reactor containment has not been purged since November 30, 1981 and durino the present steady state operation, the radioactivity has slowly increased to 39.8 maximum permissible concentration. To rerain within the ALARA guidelines, the maintenance and inspection personnel would be gequired to use respiratory protection. This requirement coupled with the 102 F containment atmosphere temperature presents considerable radioactivity and physical hazards. The District proposes to purce the containment prior to the inspection to properly decrease the radioactivity and atmospheric temperature. I have been in touch with M. Padovan during the week of January 25, 1982 and have made the following proposal. METHOD: The 66 inch purge inlet valves SFV53504 and SFV53503 will remain closed. The 12 inch ecualizing line valves SFV53610 and SFV53603 will be opened and utilized and the ventilation inlets. Thepurceoutigtvalveswillbeopenedbut SFV53605 will be administratively limited to 50% (45 ) open. These requirements should eliminate the concerns raised during your review and as discussed with me January 24th. Additionally all the aboved stated valves have been modified to assure closure during loss of DC control power or during loss of air. The purging should be initiated on January 29, 1982 and last for thirty-six hours. QUALIFICATIONS: Qualification of SFV53604 based on Allis Chalmers calculation transmitted to SMUD in their April 14, 1980 letter. This assumes a.5 second D 0 l f P AN ELECTRIC SYSTEV stRVINC MORE THAN G 0 0. 0 0 0 fN THt HEART OF C A ll f 0 R N I A i t_

4 .O* John F.-Stolz ' January 28, 1982 - 4 delay time justified by actual t'est data closure time' of'1.6 second. Qualiff-cation:of SFV53605 is based on Allis-Chalmers test report VER-0209. A maximum delay time of. l.5 second was used, as. verified by on-site testing. See attached calculation sheet below. ~ ^ . TEST _#26-1.5 second delay time. t c 0 Valve 11mited'to 45 open. Closure time: 2.5 second. I i!me from rupture to valve closure: 4.0 second. Pmax: _37.5 psig. [ Available Torque: 41,600 ft. lb. l Maximum Shaf t Torque: 13,300 ft. Ib. 4 ' Valve Dynamic Bearing Total Opgning To/T1 Building Valve Torque Torque Torque Second Press psig AP psi Ct. Ft Lb~ Ft.Lb Ft Lb 45 1.5/0 19.5 - 17.7 1.5 -4418 -1362 '3056 40 1.78/.28 21.6 19.9 0.8 2649 -1531 1118 i 30 2.34/.84 27.1 25.2 -0.4 -1677 -1939 -3616 0 20 2.89/1.39 31.2 29.1 - -0'. 8 - -3874 -2239 -6612 10 3.44/1~94 34.6 33.7 -0.9- -5074 -2593 -7639 a 0 4.0/2.5 37.5 37.5 -1.65 -10296 -2884' -13180 SFV53603 and SFV53610'are qualified in accordance with Fisher Control Company to - 'SMUD letter dated July-16,1980. : Conversations.with Fisher Controls 'have indicated that this qualification is based on testing done on smaller butterfly valves and. extrapolated to the 12" valves in'use at Rancho Seco.__ The testing'done was Lequivalent to'.the actual field conditions since neither the test nor-the field-3 conditions include.any elbows upstream of,th'e: butterfly valves. F e -,e -s m-n g a-g e p~ nm y wwem+

t' John F. Stolz January '28,1982 l - All air operated valves have been modified to fail closed upon loss of DC power - as well as loss of air pressure. A copy of Engineering Change-Notice A-3272 is enclosed describing the change'to the air control, valves. This modification has been. tested following installation by Special Test Procedure'898. 5 ohn'. Mattimoe 4 Assistant General Manager and Chief Engineer l> <, s t Subscribedgndsworntobeforeme this ffa day of April, 1982.,' l OFFICIAL SEAL _~ .,4@J PATRICIA K. GEISLER

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MAIL 1!.C SLIP A*;D I PROCES5thG SECOG IOR: ECN A-J.2 7.2, e j THIS COPY Tor MAIL STICK F!!F FWwtr STOP Originator 8b MechanicalMaint.] ~ E/M Library Electrical Shop j N.O. Designated Engr. _. MAJN C.E. Cognizant Engr. g Generation Engineering 201 Administration Surv. Engr. C. _ f3 m Switchyard Supv. Engr. E Control Room SuP. Agf. I O 2 e Outage Coordinator Supv. Engr. M i - AW J q.C. Inspector Supw. Engr. N. dU a # / tag, / ~ Training Design City ~ 32

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i '5E?S ECN N:, sc t a n ()"SMUD o"fCE. ENGINEERING CHANGE NOTICE bkTs 4..e/s r e saww for A-w sy: b uSo*dr @ THE FOLLOWING SYSTEMfSi WILL BE AFFECTED BY THIS CHANGE U Yo. K No O b In 10 CF R Section 50,59 Safety Review Requered? (See QCf 3 and QAP 2] y,, y, 9 _c"%' "' "'" M " b n a b kone e fou'l bMAna"=" !.?c,2+ 3 4 (fM_1fik'k% hf \\f& c. SW-.SW M on Mc ef dird M_R d p te r, 4e get rT+o,4 % va ut~,> ig toro ) 8 DESCRIPTION OF THIS CHANGE $NCLUDE SKETCHES AND OTHER PERTINENT AND ITS AFFECT ON PLANT OPER ATION.f LLUSTRATE HOW CH ANGE IS TO FUNC1;ON AS { PROVIDE A DET ABLED DESCRIPTION FACE (S) WITH E XISTING E Q UI PM E N T. fMDiCATE W H AT NEW CO M PON EN TIS) ARE REQUIRED AND DR AWINGS IN FORM ATION TO COMPLETELY DESCRIBE ANr) TOGETHER WIT H ESTIM ATED M ATERf AL COST.) r .' l_..... _ [ j._... 1 i .._l1. ~T 7. 1 -..l ry j g- - - - -- Sp.f g M* - - g --, _ .._g. e p 7 -.. f* ~ } hh g gg ? i e s t i / Spy ... l.... .s g(, y.. f. / \\ B A,y y y l 4 y g.d m-i ._..{ 4 l p r Por e W A*. gg r r 3 E7" : I /8 t j I# e M i - t i S'fV 3 llhbYS &t't4:11 ff sty!lt /hh 0*/ b/), B COMMENTS (indiente by whom) j SUPERVISING ENGINE E R. APPROV ALS AS INOlqATED BY h$ YTechnicen support [*[ Mectsenical d Electrical C Cwil Pf Nuclear 71nstgumentation j

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ECN No. A - T27 2-DMUD ss.., 2. a Pr.p r.d By: High et 'w QA Cl ENGINEERING CHANGE NOTICE ~ conb inwon+ pury / .. u g Tesun '"'.d forN v By: @ THE FOLLOWING SYSTEMIS) WILL BE AFFECTED BY THIS CHANGE a No a le 10 CF R Section 50 59 S.f tv Reve.w R.quer d7 (See QCl3 and,QAP 2] y,, 9 na g @ REASON FOR CHANGE _CCMumWUIN b NI2 C. b b& k =.4 % _s n. 9 e n W t _ m h o. s:v-sse m iew 4 aira + curreY& wor I a140Y -b M C d ghod W eudo_e 19,.I9P_o ) @ DESCRIPTION OF THIS CHANGE (PROVIDE A DET AILED D ESC RIPTION AND ITS A FFECT ON PLANT OPER ATION. INCLUDE SMETCHES AND OTHER PEstTINENT IN FORM ATION TO COMPLETELY DESCRIBE AND ILLUSTR ATE HOW CH ANGE R$ TO FUNCTION AS WELL AS ILLUSTR ATd INTER. FACEls) waTH EX85 TING EQ UI PM E NT. INDICATE WH AT NEW CO M PO N E N T(S) ARE REQUIRED AND DR AWINGS AFFECTED. TOGETHER WITH ESTIM ATED M ATERI AL COST.) I (....,_,.~...,. -... g Spy '["4 g- ' _ _ _ _ _ _ - Y-/S ,,[ I L. _4.__._ 1 i e .g. I 4 . ~....... .2 g, u.o. -l-.._. l i i s t -f 8 j. g j i u r S25;.*7 g .} p /,s 4 8 }I " .. f gr g ..g N.(, C t-V La _ pyy ct g y, y Qg e s s/ g i i i t --) m ~. ' [O t. t' TFf De'f//g/Ze/ (cnad&n) . Wd l V./bYS cis't? /H 1 5 COMMENTS (indicate by whom) SUPERVISINC. ENGINEER APPROVALS AS INDICATED BY [t0 l O instrum.at.t'on 0 T.cha6c.isuppo.t O u.chea6c.i O Ei.ct<6c. 0 - >is O Nucle.r-y F URTHE R APPf TOV ALS HEQUIRED PE R SUPC HVISBNG E NGINE E R O Ch.no. o poroved ey: O Issu.d for Action tay SDC. - ~~a<a m O u. .. G.... Eo...,io. O u.o.,, N.ci..,o,...t '~ . ~ ~. ,vft,yyg j//f/M ....- 1... . a. #...u ..... I c. ..,. : c..., s,..,. w. w o m,c.. Uo ..S m,.

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@ THE FOLLOWING SYSTEM (S) WILL BE AFFECTED BY THIS CHANGE p p C-ontcunvnet-Purg / ye, a No a Is to CF R Section 50.59 Se Heview Required? (See QCl 3 and QAP 2] y,, n, 9 REASON FOR CHANGE f N @GnwsbuQad-fo RQc % kano_ %'S a w 4. ure k cun M vwx: _saa_ en. n ccy p my-ewo m c o _1 owor 40 htm M._,o wovmeor. I o,.109n I @ DESCRIPTION OF THIS CHANGE (PROVIDE A DETAILED DESCRIPTION AND ITS A FFECT ON FLANT OPER A fedN. INCLUDE SKETCHES AND OTHER PERTINENT IN FORM ATION TO COMPLETELY DESCRIBE AND ILLUSTR ATE HOW CH ANGE IS TO FUNCTION AS WELL AS ILLUSTR ATE INTER. FACE (S) WITH EXISTING E QUI PM E N T. INDICATE WH AT NEW CO M PO N E N T(S) ARE REQUIRED AND DR AWINGS AFFECTED. TOGETHER WITH ESTIM ATE D M ATERI AL COST.) t [~ ~ j styr-cos) l -- - ' @352+nve) l s.e l 'l l t \\.., av gy n ---

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hbD P o g 1. S 5 -< ECNC TRANS# OftAWINMlfANGE ANSMH'r Al. - NO, Sheet of PREPAHEU BY: SUPERVISING ENGINEEH ASSIGNED: D h acs L. 3kplar7 son C o r, P4 4 7 A P4 T / D r c,, r. P4 F PJr i PJ E E R OATE t i!ITZ IX XOI'.1 Y.4 T/'R 87 V4 f ? DCN NUMBER IF NEW DRAWING BY SDC/GEC WRITE NEW" M DISCIPLINE -(Check one) DCN ORAWING NO. L,RAWING NUMBER APERTURE Sht. No. l Rev. CARD NO. O ELECTRICAL I-92 2 I / ASE155 a c'" I-927 I 5 ABE /Go--- - - -- - O INSTRUMENTATION O NUCLEAR I b b_b b _ 8 AR$ OTHER dlSCIPLINES INVOLVED? /es p ~ E-20_3 C4A oIABB_Z47_ 0 *'"/ a no \\ E-203 448\\ / 'A28 7d8

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) s, 4:2c4-6 ? SACRAMENTO MUNICIPAL UTILITY DISIRICT,. f.} gl," *l OFFICE MEMORANDUM g., g -. - - To: D. G. Raasch DATE: November 19, 1980 RJR 80-604 FROM: R. J. Rodriguez ' cuBJECT: Containment Bui.lding Integrity L. In the November 19, 1980 reply to Region V, the General Manager stated that the final corrective action for 'the air-operated containment purge valves would be taken during the 1981. refueling outage. This will require additional valves being procured and available by the time we shut down in May. I request that Generation Engineering proceed with the final design and procurement so that ins tallation can be completed. before our return to power in the late spring of 1981. D RJR:jr cs: Oubre' s ,/" e e w..- O l l l O %g w ew 888 CD se.

1. .CESCNPTI0ft: A design modift:stion to provide a failsafe conaition for valve srV-53604 ole less of direct.urrent pcwer, also for valves SFV-53503 and SFV-53610. f;CR ECr: A-3272 2. SAFETY Ai!ALYSIS: See attached Design Basis Report. b'< * })g7&o // ,,./ ,, M :',- - / - G-B . /Sy *st tre.v * / if /.79.l;2 p,. v Licensing Engioter vate Manager Generation Engineering Date 3. PRC RECOMPEi! DATIO:1: 50.59(c) Yes O No S 50.59(b) Yes @ f!o O DISPOSITICf! 0F PRC: a. Unanimously recommends proposal 2 d. Safety analysis inadequate O b. Send to MSRC for concurrence y e. MSRC ^ review prior to implementing [ c. Recommends not to proceed O f. Test of system re uired g h.g bfkvdb/ .s PRC Chairman Date 4 ANALYSIS: ~0. 5 E ( c. ) Yes C Recommend to Proceed Yes @ ?!o O No g Refer to MSRC Z 50.59(b) Yes g Test of system reouired @ .__%C6sa%2_ t - iM z.- Plant Suoerintencent Date 5.. MSRC FINDII:GS: 50.59(a) Yes O flo O 50.59(b) Yes C fio O DISPOSITIOil 0F MSRC: a. Recommends proposal O c. Recommends not to proceed O b. Send to NRC for approval C d. Safety analysis inadequate C PSRC Chairman Date ~ 6. CONMISSION APPRDVAL DSTA!i:ED Date MSRC Chairman 7. RETEST COMPLETE AND ACCEPTABLE: Test results approved Supervisor Enoineering and Ouality Control S. OVERALL REVIEW: Plant modification. change complete. Manacer :or loar Onera ti. nc. 0 9.' 3. CXUE'JATiON COMPLETE: d u : 1 i L.',- ,,urano: J i cc *.u: N te . iu a, u.,.a u,,,dMMM. ' N NE=7fh N O "d=' M ' ~fiMYI[U-MM *I[ ~ w

) e ENGINEERING ASSIGNMENT SHEET FOR ECN NO.A'82 57 Date: Design Basis Second Level Discipline Engineer Report Reauired Review Engineer EEr' Cognizant Engineer Y.

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8N O Civil Engineer O O Electric Design Engineer O O I & C Design Engineer O O Mechanical Design Engineer O t O Nuclear Design Engineer O GEP'Cicensing Engineer (50.59s) Bob Dieterich O 8 24N INSTRUCTIONS: 1. The Manager of Generation Engineering will assign the Cognizant Engineer and will indicate,in the square following the Cognizant Engineer's name, where a Design Basis Report is required. 2. The Manager of Generation Engineering will also identify those ECN's that require a Safety Analysis Report by the Licensing Engineer, as well as the Second Level Review Engineer for the Safety Analysis. 3. All other assignments required will be made by the Cognizant Engineer with the concurrence of the appro-priate Supervising Engineer. The Manager of Generation Engineering may make suggestions by marking certain boxes or identifying certain engineers for some or all of these activities, but these are only sug-gestions and should be treated accordingly. Under all conditions, the Cognizant Engineer must notify the personnel assigned and clear the assignment with the Supervising Engineer. 4. The Design Basis Report may be prepared by the Cognizant Engineer or may be assigned to one or more design engineers on complex projects. Remember, each Design Basis Report requires a Second Level Review. The Cognizant Engineer shall also assign these personnel, with the concurrence of the Supervising Engineer. Wf"W l D. G.' Raasch Manager, Generation Engineering i l l prusw,;;amsnsw.wwanw n n m **** ** * *** W A'* y

Log.3JM__EIN 1. DESIGli BASIS REPORT ECt! 2-3272. t!CR N/A WOllK REQUEST _104195 Discipline I&C Date Jan. IL.1212 I. P_URPOSE OF DESLQ11 fflAt!GE : The purpose of this design change is to implement the requirements of 10 CFR Part 50, Appendix A, Criterion 23 by providing valve closure on loss of direct current power. This is further defincd in the Districtfs letter to the !!RC, dated tiovember 19, 1980. " District engineers have designed a modification to the system which will provide a closure signal on loss of direct current pouer. Upon completion of this modification, the valves in question will fully meet all the requirements of 10 CFR Part 50, Appendix A, Criterion 23." II. DESIGi! CRITERIA USED: 1. Solenoid valves shall be Class IE and shall meet the requirements with respect to separation, seismic and Environmental Qualification. 2. The following codes and standards are applicable to the solenoid valves purchase and installation. Sp_onsor !! umber Subject IEEE 323 Quality Class lE Equipment for Nuclear Power Generating Stations. IEEE 344 Recommended practices for Seismic Qualification of Class IE equipment for Nuclear Power Generating Stations. III. CALCULATIO!1S RID DESIGN IllEORMATIOll: 1. Installation of the solenoid valves meet the requirements for Class IE safety grade. Conduit runs and cables will remain as previously installed. 2. Valves SFV 53503 and SFV 53504 require 3 solenoid valves in parallel to assure a 5 second closing time. This is achieved by matching the C of the y existing solenoid valves to the C of the y r epl a ce;aen t solenoid valves. page 1 of 2 42 %<w*pnwe.wum)w;engw.tc.sa%%+.smww %-gusmmggy-m4:4.,g y e

e 3. Velve SPV 53610 requires an exact replacement of the solenoid valve. 4. The attached drawing '1-551 identifies the system con-figuration to meet the tinc requirement. IV. FAILURE MODE: A credible failure resulting in a pipe break of any of the associated piping will result in the loss of control air to the valve actuator and the associated containment isolation valve will fail closed. A credible failure of any of the associated wiring (i.e., short circuit, open circuit) will result in failure of power to the valves which will then fail in the SFAS (safe) actuated state. V. COftttENTS: The design meets the requirements of 10 CPR Part 50, Appendix A, criterion 23 and is in compliance with the District's committment to the 11RC. Design Engineer / Date /-/_S '32-JV/ Review Engineer 72 L ^ c?BL rr Fet> Date 1-6 62 5 \\ page 2 of 2 M%%Dw'6&ttE 4AM%

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.u..; November 19, 1980 'J k, o- _N?* c,.,,7 Mr. R. H. Engelken. Director Region V Of fice of Inspection & Enforcement U. S. Pluclear Regulatory Co mission 1990 iforth California Boulevard Walnut Creek Plaza, Suite 202 9alnut Creek, California 94936 Re: J. L. Crews to J. J. Mattimt.,e Letter Dated tJovember 7,1980 Operating License DPR-54 ~ Docket tio. 50-31

Dear Mr. Engelken:

In reply to your letter from Mr. J. L. Crews reques ting an additional response to item C of the t otice of Violation. dated September 26, 1980, we offer the following explanations and corrective actions to assure full. compliance with flRC' requirements. Appendix A, i tem C of the September'26*,1980 letter notes the following infraction: 10 CFR Part 50, Appendix A, Criterion 23 states that the protection system shall be designed to fail into' a safe state or into a state demonstrated to be acceptable on some other defined basis if conditions such as disconnection .[ of the. system, loss of energy (e.g., electric power, instrument air), or postulated eJverse environments (e.g. extreme heat or cold, fire, pressure, steam, water, and radiation) are expe rienced. ~ In the FSAR Appendix lA, Page IA-26 as part of a discussion on Criterion 23. the licensee states, " Safety ' features ' equipment can be.~ar. bally initiated by the operator at ar.y time even if power is lost to the actuation system." Contrary to the above the reae. tor building purge inlet line valve SF'! 53503, the reactor building purge outlet line valve SFV 53604, and the reactor building pressure equalizing line valve SFV 53210 will apparently fail open on loss of direct current power to the solenoid operators. f.!k' !O 0 /. } E .L, V- ,/ 7g - r J g.7, w, a..m.. _ ~~, ,.m -q

/ N bs ' O -O - ) Mr. R. H. Eng21k:n Nov:mb r 19, 1980 - i, j SMUD Reply As stated above, the three' valves do presently fail in the open position on a loss of direct current peaer to the controllir.g solenoid valves. Since the valves in question are all outside containeent valves wi th a fully redundant inside containment motor-opera ted valve, con tainmen t integrity would not be violated u;:en loss of direct current power to the solenoid. However, to furtner assure containment integrity, it was decidea to isolate the air to the three valves in ques tion whenever reactor building containment integrity is recuired. Sasically, this " fails" the valves in their respective safety features positions and subsequent loss of direct current power to the solenoid operators will not al ter the position of the valve. The above corrective action has been implemented as an interim solution. D,istrict engineers have designed a codification to the system which will provide a closure signal on loss of direct current ' power. Upon completion of this codification, the valves in question will fully meet all the requirerents of 10 CFR Part 50, Appendix A, Criterion 23. It is the District's intention to make these modifications during the 1981 refueling ou tage. Sincergiy, ?'l m. m. Vm. C. Valbridge encral Manager WCV:HH:Jr G o O e 9 s O .= e e 4 a 6 ee ,.o a ,pgme em.= g - - ~.- - -.-..

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