ML19257D220
| ML19257D220 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/22/1980 |
| From: | Dieterick R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19257D211 | List: |
| References | |
| NUDOCS 8002010542 | |
| Download: ML19257D220 (6) | |
Text
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I January 22, 1980 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
)
)
SACRAMENTO MUNICIPAL UTILITY DISTRICT
)
Docket No. 50-312
)
(Rancho Seco Nuclear Generating
)
Station)
)
AFFIDAVIT OF ROBERT A.
DIETERICH County of Sacramento )
ss State of California
)
Robert A. Dieterich, being duly sworn according to law, deposes and says as follows:
1.
I am a Senior Nuclear Engineer in the Generation Engineering Department of the Sacramento Municipal Utility District
(" Licensee") and give this affidavit in support of Licensee's Motion for Summary Disposition of Contentions by Intervenors Gary Hursh and Richard Castro.
I have personal knowledge of the matters set forth herein and believe them to be true and correct.
A summary of my professional quali-fications and experience is attached as Exhibit "A" hereto.
2.
Contention 3 advanced by Intervenors Gary Hursh and Richard Castro (H/C Contention 3) alleges that Rancho Seco "has a lack of direct initiation of reactor trip upon 1857 085 SR 8002010
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the occurrence of off-normal conditions in the feedwater system..."
Contrary to this contention, addition of a hard-wired control-grade direct reactor trip upon the occur-rence of a loss of feedwater was proposed by Licensee in a letter dated April 27, 1979 to the Commission (Exhibit "B").
In its May 7, 1979 Order, the Commission approved performance of these modifications, which were installed by Licensee on or cbout May 14, 1979 (Exhibit "C"),
successfully tested on or before May 29, 1979 (Exhibit "D")
and approved by the Commission staff in its June 27, 1979 Safety Evaluation (Exhibit "E"),
in which the staff concluded at page 16 that "there is reasonable assurance that the [ trip circuitryl system will perform its function."
Such a hard-wired direct reactor trip capability remains in place at Rancho Seco and I believe it to be fully operational.
3.
H/C Contention 5 alleges that Rancho Seco "has an actuation before reactor trip of a pilot-operated relief valve in the primary system pressurizer..."
Contrary to this contention, the Commission staff requested on April 21, 1979 (IE Bulletin 79-05B at page 3) (Exhibit "F")
that Licensee consider modifying the setpoints for the high pressure scram and the pilot-operated relief valve (PORV) to reduce the likelihood of automatic actuation of the PORV during transients.
In response to this request, Licensee notified the Commission in a letter dated April 22, 1979 (Exhibit "G")
that the 1857 086
system high primary pressure reactor trip setpoint had been lowered from 2355 psig to 2300 psig maximum, and that the PORV setpoint had been raised from 2255 to 2450 psig nominal so as to ensure that the reactor trip occurs before PORV actuation.
On July 2, 1979, Licensee (following a cirective from the Commission staff--see Exhibit "E"
at page 2) modi-fied the Rancho Seco Technical Specifications to incorporate permanently the new setpoints for system high primary pres-sure trip and PORV actuation into the plant's limiting con-ditions for operation (Exhibit "H"),
and such setpoints will remain in effect until instructions to the contrary are is-sued by the Commission.
These modified setpoints greatly reduce the probability that there will be actuation of the PORV during a transient.
4.
H/C Contention 9 alleges that Rancho Seco "has not installed adequate hard-wire control grade reactor trip on loss of main feedwater and/or on turbine trip..."
Contrary to this contention, and as noted above with respect to H/C Contention 3, hard-wire control grade reactor trips on loss of main feedwater and/or on turbine trip were in-stalled at Rancho Seco in May, 1979, and the circuitry and other modifications introduced to implement these features were tested by Licensee, analyzed by the Commission staff, and found satisfactory in the June 27, 1979 Safety Evaluation (Exhibit "E").
1857 087 5.
The hard-wire control grade reactor trip on loss of main feedwater and/or turbine trip circuitry has been designed to the highest industry st.ndards to provide high reliability of operation.
This circuitry has operated successfully in two loss-of-feedw
- transients and two turbine trips at Rancho Seco, and has been tested monthly without failure.
This circuitry is also comparable in quality and reliability to other control grade circuitry installed at Rancho Seco (for instance, the turbine-generator controls) which has proved extremely reliable in over five years of operation.
It is my opinion, therefore, that the hard-wire control grade reactor trips on loss of main feedwater and/or turbine trip are more than adequate in terms of reliability.
6.
H/C Contention 20 alleges that Rancho Seco "does not have a hydrogen recombiner which may be necessary in the event of an accident caused by a loss-o f-feedwate r transient,
and therefore is unsafe and endangers the health and safety of petitioners, constituents of petitioners and the public."
While it is true that Licensee does not own a hydrogen re-combiner, Rancho Seco is designed to dispose of any hydrogen accumulation within the containment building by purging it instead of recombining.
In the maximum hypothetical accident with one percent fuel failure, it would not be necessary to start purging hydrogen until 770 hours0.00891 days <br />0.214 hours <br />0.00127 weeks <br />2.92985e-4 months <br /> after initiation of the accident.
185/
088
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i 7.
Even assuming that a hydrogen recombiner were ever needed at Rancho Seco, Licensee has entered into a contract (Exhibit "I")
with the Arizona Public Service Company (APS) under which c?S will loan to Licensee its hydrogen recombiner, Serial No. 110B. currently in storage at the Palo Verde Nuclear Generating Station, promptly upon Licensee's request.
I estimate that APS' hydrogen recombiner would be delivered to the Rancho Seco site within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of its being requested from APS.
It is also my opinion that, if one assumes that a hydrogen recombiner will be required in the event of "an accident caused by a loss-of-feedwater transient," the need for a recombiner would not. arise until several days after the initiation of the accident, thereby giving ample time for shipping and installation of the APS hydrogen recombiner at Rancho Seco.
- (
r L ft (LLt-Robert A.
Dieterich Subscribed and sworn to before me this SW day of January, l'380.
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>J Notary Public 0FFICI AL SEAL l
.x PATRICIA K. GEISLER NOT Aav % Otic CAuf 04NiA Qg g/4 y Pw Qr1L OFPcE IN sacW AMENTO COUNTY My Commiss:en Eores Naemte 22 1933 l
i857 089 9
8 ROBERT A. DIETERICH Professional Qualification and Experience Robert A. Dieterich is a Senior Nuclear Engineer in SMUD's Generation Engineering Department. Mr. Dieterich is a graduate of the University of Kansas with a Bachelor of Science degree in Engineering Physics, with a major area of study in nuclear engineering.
He has also taken graduate level courses in nuclear engineering from the University of Washington while employed by the General Electric Company in that state.
M.
Dieterich worked for three years as a Process Physicist for the Gener el Electric Company at the Hanford operations in Richland, Washington.
In this position he performed all routine physics calculations for an assigned plutonium production reactor, providing fuel loading patterns and operating techniques consistet with established safety criteria. Following this period, Mr. Dieterich accepted a position as a Nuclear Engineer with the General Elec ric Company in their Nuclear Energy Division in San Jose, C:liifornia.
In this position he performed analyses of design basis reactivity accidents for safety anslysis reports.
He also participated in the licencing efforts for the Oyster Creek and Nine Mile Point nuclear power plants, and had total responsibility for the preparation of the Nine Mile Point and Monticello technical specifications.
Following his employment with the General Electric Company, Mr. Dieterich accepted a position with the Sacramento Municipal Utility District, where he has been employed for the last nine years.
Mr. Dieterich is presently a Senior Nuclear Engineer in the Generation Engineering Department and has had responsibilities in the design, erection, startup and licensing of Rancho Seco.
Mr. Dieterich is a member of Sigma Pi Sigma (a physics honorary society) and the American Nuclear Society.
Mr. Dieterich is currently registered as a Professional Nuclear Engineer in the state of California, registration number N103.
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Acril 27,1979 Mr. Harold R. Den =n Direcer Offica of Nuclear React:r Regula:ica USNRC Washing :n, D. C.
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Ranch Seca Nuclear Station Cccket Nc. 50-312 Dest Mr. Den = n:
the staff safety c ncer.s ideniified as itz:s 1. thr:ugn In res:ense :
- e. en cage 1-7 cf the CNRR Sta=s Recer; := ce C= mission of At.ril 25, 1979, tne Sacrament Municipal Utili y Distict pre;cses -he fcilcwing acticns:
(a)
Upgrade of the timeliness and reliability cf delivery fr=n the Auxiliary Feecwater Sys.ma by car ying cut itans 1 through 9 identified in encictsrs 1.
(b)
Cevelep and implement ;cerating precedures f:r initiating
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and cenrolling auxiliary feecwater indecenden: cf ICS cen:r:1.
(c)
Im:lement a hardwired c:n: 01-;rade react:r trip cn icss cf main feedwatar and/cr turbine t-fp.
(d)
Cemcleta analyses fcr ;ctantial small breaks and deveic: and im:lemen: cperating ins:-:cticns = define = erat:r acticn.
(e)
Tne Disrict will crevide for ene Senicr Licensed C;erser assigned to tne c:nrei recm wnc has had DiI-2 training en the B&W simulat:r.
Rancho See will be shutdcwn en Acril 23, 1979 and will ne: be restartad until iten a. thr ugn e. abcVe are c= pleted.
he Disrict further c=mits :: the fellcwing addi:icnal acticns fcr im revemen and in assuring safety that is relatad = itams a. thr ugn
- e. in ONRR Sta us Recer cf Acril 25, 1979:
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UNITED STATES f h,Jyg,j NUCLEAR REGULATORY COMMISSION g
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June 27, 1979 Docket No. 50-312 Mr. J. J. Mattimee Assistant General Manager and Chief Engineer Sacramento Municipal Utlity District-6201 S Street P. O. Box 15830 Sacramento, California 95813
Dear Mr. Mattimoe:
By Order of May 7,1979, the Commission confimed your undertaking a series of actions, both ir=ediate and long tem, to increase the capability and reliability of the Rancho Seco Nuclear Generating Station to respond to various transient events.
In addition, the Order confimed that you would shut dcwn Rancho Seco on April 28, 1979, and maintain the plant in a shut-down condition until the follcwing actions had been satisfactorily empleted:
(a)
Upgrade the timeliness and ieliability of delivery frm the Auxiliary Feedwater System by carrying out actions as identified in Enclosure 1 of your letter of April 27, 1979.
(b)
Develop and implement operating procedures for initiating and controlling auxiliary feedwater independent of Integrated Control System control.
(c)
Implement a hard-wired control-grade reactor trip that would be actuated on loss of main feedwater and/or turoine trip.
(d)
Complete analyses for potential small breaks and develop and implement operating instructions to define operator action.
(e)
Provide for one Senior Licensed Operator assigned to the control room who has had Three Mile Island Unit No. 2 (TMI-2) training on the B&W simulator.
By submittal of May 14, 1979, as supplemented by seven letters dated May 22, 24,29,30(3) and June 6,1979, you have documented the actions taken in response to the May 7 Order.
We have reviewed this succittal, and are satisfied that, with respect to Rancho Seco, you have satisfactorily completed the actions a['G 2D QL a
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Mr. J. J. Mattimoe.
prescribed in items (a) through (e) of paragraph (1) of Section IV of the Order, the specified analyses are acceptable, and the specified implementing procedures are apprcpriate.
The bases for these conclusions are set forth in the enciesed Safety Evaluation.
As noted on page 13 of the Safety Evaluation, you will be required to conduct a test during pcwer operation to demonstrate operator capability to assume manual control of the Auxiliary Feedwater System independent of the Inte-grated Control System.
Appropriate Technical Specifications for Limiting Conditions for Operation and for surveillance recuirements should be developed as soon as practicable and provided to the staff within seven days with regard to the design and procedural changes which have been ccmpleted 4 ccmoliance with the provisions of the May 7,1979 Ccmmission Order.
The rer -Of Technical Scecifications should cover:
(1) Addition of ficw indication to the Auxiliary Feedwater System; (2) Addition of the Anticipatory Reactor Trips; and (3)
Changes in set points for high pressure reactor trip and PORY actuation.
Within 30 days of receipt of this letter, ycu should provide us with your schedule for completion of the long tenn modifications described in Section II of S ? May 7 Order, and you should submit for staff review the mcdel used in the analysis for potential small breaks referenced in ycur letter of May 14, 1979, e
My finding of satisfactory comp".iance with the requirements of items (a) through (e) of paragraph (1) of Section IV of the Order will pennit resumption of operation in accordance with the terms of the Ccmmission's Order; it in no way affects your duty to continue in effect all of the above provisions of the Order pending your submission and approval by the Ccmmission of the Technical Specifi-cation changes necessary for each of the required mcdifications.
Si ncerely, 3-pW g Harold R. De on, Director Office of Nuclear Reactor Regulation
Enclosures:
1.
Safety Evaluation 2.
Notice cc w/ enclosures:
See next page
EVALUATION OF LICENSEE'S CCMPLIANCE WITH THE NRC ORDER DATED MAY 7, 1979 SACRAMENTO HUNICIPAL UTILITY DISTRICT r
RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 DUPLICATE DOCUMENT Entire document previously entered into s stem under:
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R. J. Rodriguez, SMUD L. G. Scr.wieger, SMJO 1857 097 i
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s Description of Circumstances:
Continued liRC evaluation of the nuclear incident at Three Mile Island Unit 2 has identified measures in addition to those discussed in I~ Bulletin 79-05 and 79-05A 'i".ich shoJ1d be acted upon by licensees with reactors designed by B F.l.
As di::ussed in It=. l.c. of Actions o be tasen by Licensees in IES79-05A, the preferred made of core cooling following a transient or accident is to pro-vide f;rce; fl '.-i using reactor coolant pumas.
It appears that natural circulation.sas not successfully achieved upon sacuring the react ^r coolant pum;s during the first t.ia hours of the Three Mile Island (T"I) ha. 2 'acident of.! arch 25, 1979.
Initiation of natural circulation ias s4 o
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condensible gases, in the primary coolant system To avoid this potential for interference. tith natural circulation, the operator should ensure that the primary system is subcooled, and remains subcooled, befcre any attempt is made to establish natural circulation.
T;autural circulation in 315 ock and Wilcox reactor systems is enhanced by maintaining a relatively high.iater level on the secondary side of the once through s team generators 7,i so).
It is a, iso promoteu by injection or auxl,iiary u
y s
feed.!ater at the uoper nozzles in the GT5Gs.
The ir,tegra ted Control System au*.cmatically sets the OTSG level setpoint to 50t on the operating range when all reactor coolant pumps (RCP) are secured.
Ecwever, in unusual or abnormal situations, manual actions by the operator to increase steam generator level will enchance natural circulation capability in anticipation of a possible loss of operation of the reactor coolant pumps.
As stated previously, forced fic.i of primary coolant through the core is preferred to latural circulation.
Other means of reducing the possibility of void formation in t' e reactor coolant r
system are:
A.
Minimize the operation of the Power Operated Relief Valve (PCRV) on the pressurizer cr.d thereby reduce the possibility of pressure reduction by a bicwdnwn thr :;h a PORV that was stuck open.
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~ g.m a,e,. N ~:.s m-3 "w S Ac.v M DTC ',N.'.10:FAL UT:u v 0:STR:07 - C' S S:reet 6 '!!I. Sacrar en*:. C e fernia 09:2. MO r!2.:<.:: July 2, 1979 Direc:or o f ';uclear oeactor Regulation Attention: Mr. Rober: Reid, Chief Operating Peae: ors, 3 ranch No. 4 U. S. Nuclear Regula.-
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.o =u a' ~. .'..S. 4.. s.' v e.. m' a- ~f s a o e m',. '. a =. '.s."....4..=' .C.,2..' 4_ m.'. i. v-.. e. ..... d.;.".i.'.'v'..s ".. - -...- pliance with :be Order of May 7 1979. Find at: ached :he r2;u'.remen:s for t 4.,1. :., -, .a.a.,.n=- 2 : .c.,,,,.. c,,a.e.2.. c. s.. o..w,... e.. ... Ope..,.4.a anu .,sa....,..... s the modifica: ions including: 1) Addition of fic indica ica to the Auxiliary Feedwater System. .? ) .Ad d 4..' o. e.#.'.e.'..-...'.a...:-
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u .a 3) Changes i., se: :oints for high pressure reac:or : rip 2nc FOR'i ac:ua tion.
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