ML19257D221
| ML19257D221 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/22/1980 |
| From: | Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19257D211 | List: |
| References | |
| NUDOCS 8002010544 | |
| Download: ML19257D221 (4) | |
Text
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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)
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AFFIDAVIT OF R. J. RODRIGUEZ County of Sc.eramento
)
SS State of California
)
R. J. Rodriguez, being duly sworn according to law, deposes and says as follows:
1.
I am Manager, Nuclear Operations 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 qualifications and experience is attached as Exhibit "A" hereto.
2.
Contention 8 advanced by Intervenors Gary Hursh and Richard Castro ("H/C Contention 8") alleges that Rancho Seco "does not have operating procedures for initiating and controlling the emergency feedwater system independent of the integrated control systeni control...." Contrary to this contention, Licensee proposed in a letter dated April 27, 1979, to the Commission (Exhibit "B") to "[d]evelop and imp 1.ement operating procedures 1857 101 paa no 94 5 %
for initiating and controlling auxiliary feedwater independent of ICS control."
This proposed modification was accepted by the Comission in its May 7,1979 Order, and the auxiliary feedwater procedures were modified by Licensee (Exhibit "C").
The revised procedures were reviewed by the Comission staff, which also walked through them with the Rancho Seco operators and audited a sample of the the operators to determine if they were familiar with the revised procedures and could implement them correctly. The staff concluded "that the revised procedures and operator training are satisfactory" (Exhibit "D", p. 5-6, 13). These revised procedures for initiating and controlling auxiliary feedwater independent of ICS control remain in effect and will be fully complied with when applicable.
3.
H/C Contention 22 alleges that Rancho Seco "does not provide control room operators with sufificient data on the water level in the pressurizer and vessel because the operators must interpret information on temperature and pressure on the primary loop and extrapolate water level...".
Contrary to this contention, as long as reactor coolant temperature and '
pressure are maintained in a subcooled condition, pressurizer level (which is available directly to the operators in the control room) is a direct and adequate indicator of system water level. Moreover, during the current outage a subcooling indicator will be installed which, together with the pressurizer level reading, will eliminate any need for interpretation of temperature and pressure data.
4.
H/C Contention 25 alleges that Rancho Seco "does not have control room instrumentation which would indicate if the auxiliary feedwater or pressurizer relief valves are open or closed or the instrumentation to open or close such valves automatically...".
Contrary to this contention, the addition of instrumentation to provide indication of AFW flow to each steam generator was proposed by Licensee in its April 27, 1979 letter to the Commission (Enciosure 1, item 5).
Performance of this modification 1857 102
was approved by the Commission in its May 7,1979 Order, and the modification was then implemented by the Licensee.
On June 27, 1979, the Conmission staff reviewed the Licensee's implementation of AFW flow rate indication and the results of tests of this implementation, and concluded that the modifi-cation had been properly implemented (Exhibit "D", page 8).
The AFW flow inctrumentation indicates both the position of the valves and whether pumps are runr.ing.
5.
Licensee is also in the process of adding instrumentation to indicate pressurizer relief valve position. Such instrumentation is being installed on the pressurizer valve discharge piping during the current outage,with the exception of some signal processing equipment which has been ordered, is scheduled for delivery at Rancho Seco by May 1,1980 and will be operational approximately by June 1,1980.
The instrumentation to be added will provide indication in the control room of valve position.
6.
Also contrary to this contention, the pressurizer re'ief valve opens and closes automatically on pressure. A block valve in series with the pressurizer relief valve may be operated remotely from the control room.
Auxiliary feedwater valves which are normally closed and need to open for initiation of auxiliary feedwater do open automatically.
There are certain auxiliary feedwater valves which are normally in the open position, and are therefore locked open so no automatica eration is required.
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Subscribed and sworn to before 1857 103 me this J7 7 day of January, 1980.
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RONALD J. RODRIGUEZ Professional Qualification and Experience Ronald J. Rodriguez is Manager of Nuclear Operations for the Sacramento Municipal Utility District.
Mr. Rodriguez is a graduate of the United States Naval Academy, with a Bachelor of Science degree in Naval Science.
He has completed the Navy nuclear power graduate-level technology course, the six-week Babcock & Wilcox reactor technology course, and a ten-week Nuclear Steam Supply System Simulator Training Program presented by Babcock & Wilcox.
For eight years Mr. Rodriguez was a commissioned naval officer, serving primarily in the Navy Submarine Program.
For three years he served in engineering positions onboard an operating nuclear-powered submarine.
His areas of responsibility varied among reactor plant systems, main propulsion systems, electrical and reactor instrumentation systems, chemistry, and health physics control for maintenance and personnel protection.
For two years he was assigned as a training officer, responsible for training Navy Nuclear Power Officer and Enlisted candidates at the Navy's training facility located in Windsor, Connecticut. This assignment gave him responsibility for administration of all classroom training, in-plant training progress, and final examination for qualification for Nuclear Power Plant Operators and Watch Officers.
His final responsibility in the Navy was as Chief Engineer of a nuclear power submarine.
In this capacity he had responsi-bility for the administration of an Engineering Department, which included qualification and training of reactor operators and power plant watch standers.
After joining SMUD in 1968, he served as Assistant Superintendent for Nuclear Operations until February,1970.
During this period of time, he was responsible for establishing the initial phases of the Rancho Seco Operator Training Program and the selection and hiring of plant operating personnel.
From March, 1970, until January, 1978, he was Plant Superintendent, with direct responsibility for the testing and startup program for Rancho Seco, including the staffing for Operations, Technical Support and Maintenance personnel.
He was also responsible for the overall diraction of vendor personnel assisting in the startup program, and served as chairman of the group established to provide final approval of the functional test program.
Since January, 1978, he has been Manager of Nuclear Operations, with department level responsibility for the safe and proper operation of Rancho Seco.
Mr. Rodriguez has participated in the entire Licensing Training Program at Rancho Seco and currently holds a Senior Reactor Operator License.
He is currentiy a member of the Electric Power Research Institute's Engineering and Operations Task Force, a member of the American Nuclear Society's Reactor Operations and Support System Management Committee, and a member of the Atomic Industrial Forum's c'erational committee involved in the initial establishment of the Institute of Nuclear Power Operations.
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2C555 anca.c sec Nuclear.e,20 en se:
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Dear Mr. Dent:
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- ne s 2ff safety =ncarns ideniifiec as itz:s 1.
-hr ugn In ris:ense ::
- e. en : age 1-7 ef ne CNRR 5:2::s Recer..: Se C.:nnissien cf Acril 25, 1979, tne Sac =ent: Munici;al Utilir! Disric; :r ;cses ne f:ilcwing actiens:
(a)
Ucgrade cf the ti=eiiness and reliabilir/ cf deliverf f-ci r.e Auxiliar/ secnatar Systan by car yinc cut itans i thrcugn 9 icen-ified in encicart 1.
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(b)
Ceveicp and i=:lenen: ccer:t'ng pr:cadurss fer ini-iating and c:nr lling auxiliarf feecwatar indecenden: ef ICS c:n e:1.
(c)
I= leren: a hardwired c:nr:1-;r2de mac :r tri; en icss cf ain feeenatar and/cr :;r ine ri:.
(d)
C.:n::lete analyses fcr ;ctantial
- all breaks and devele: anc i=:lenen: ecerating ins : acticns :: define = erat:r actien.
( e)' Re Disrict will :r: vide f:r cne Senier Licensed C:erz.:r assigned = ce c:nrei rec = wne has had NI-2 :rsining en the S&W simulat:r.
Ranch: Sec: will be shu dewn en April 23, 1979 and will act be. tstartad until itan a. tar:ugn e. above are c=npleted.
He Disrict further :=nnit O the fellcwing adciticnal acticns fcr i=:revenen; anc f n assuring safer / ta: is tiat2d.c i en:s a. thr ugh
- e. in CNRR Sta us Recer cf Acril 25, 1979:
DUPLICATE DOCUMENT Entire document previously
- *f y i entered into system under:
hNO 1857 103 No. of pages: