Letter Sequence Request |
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Results
Other: ML19210C119, ML19247B236, ML19250A524, ML19250A528, ML19257B027, ML19260C126, ML19260C878, ML19309A657, ML19309B061, ML19309B071, ML19317G911, ML19317G973, ML19317G984, ML19330B670, ML19332A733, ML19337A632, ML19345F375, ML20148E958
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MONTHYEARML19319E1821976-08-12012 August 1976 Requests Info Re Facility Vulnerability to Plant Operation & Equipment Failures During Degraded Grid Voltage Conditions Similar to Millstone 2 Jul 1976 Occurrence.Description of Millstone 2 Event & Request for Addl Info Encl Project stage: RAI ML19309B0611976-09-17017 September 1976 Responds to NRC 760812 Info Request Re Grid Voltage Degradation Effects on Class IE Electrical Distribution Sys. Defines Facility Operating Limits Established by Grid Stability Analysis & Discusses Electrical Sys Capabilities Project stage: Other ML19317G8981977-06-0303 June 1977 Forwards NRC Safety Evaluation & Model Tech Specs Re Emergency Power Sys.Util Requested to Submit OL Amend Application Incorporating Tech Specs Comparable to Model Tech Specs Project stage: Approval ML19317G9111977-06-0303 June 1977 Model Tech Spec Tables 3.3,3.3-4 & 4.3-2 Re Engineered Safety Feature Actuation Sys Instrumentation & Section 4.8.1 Concerning Surveillance Requirements of Electrical Power Sys Project stage: Other ML19317G9731977-07-19019 July 1977 Responds to NRC 770603 Info Request.Discusses Facility Second Level Voltage Protection,Undervoltage Scheme Mods, Emergency Bus Load Shedding Features & Tech Spec Test Requirement Demonstrating Onsite Power Source Operability Project stage: Other ML19317G9841977-10-10010 October 1977 Responds to NRC 771005 Telcon.Submits Util Schedule for Emergency Power Sys Redesign Work,Tech Spec Mod & Mod Completion Project stage: Other ML19309B0711978-01-0909 January 1978 Discusses Commitment to Installation During Aug-Sept 1978 Refueling Outage of Second Level Voltage Protection Sys for Nuclear Svc Buses W/Coincident Logic Per NRC Project stage: Other ML19309A6571978-06-20020 June 1978 Proposed Amend 51 to License DPR-54.Includes Tech Specs 4.1 Re Instrument Surveillance Requirements Project stage: Other ML19309A6551978-06-20020 June 1978 Forwards Proposed Amend 51 to License DPR-54.Tech Specs 4.1 Re Instrument Surveillance Requirements Drafted in Response to NRC 770603 Request for Review of Onsite Emergency Power Sys Project stage: Draft Request ML20148E9581978-10-31031 October 1978 Notifies That Util Cannot Obtain NRC Approval,Perform Calculations & Purchase New Equipment for Installation of Second Level of Voltage Protection by 1978 Refueling Outage. Proposes Mod Completion by End of 1979-80 Refueling Outage Project stage: Other ML19257B0271979-04-12012 April 1979 Forwards Background Info on 780916 AO at Facility & Sample Generic Ltr to Licensees Re Adequacy of Station Electric Distribution Sys Voltages Project stage: Other ML19242A4121979-06-26026 June 1979 Transcript of 790626 Meeting in Washington,Dc.Pp 1-55 Project stage: Request ML19274F9791979-07-18018 July 1979 Forwards Request for Addl Info Re Degraded Grid Voltage, to Be Sent to Licensee in Order to Complete Review of 771010 Submittal.Response Required within 45 Days Project stage: RAI ML19208C3621979-07-23023 July 1979 Submits Contention in Support of Request for Hearing.Plant Endangers Health & Safety of Population.Sufficient Mods Have Not Been Made Re TMI.Long-term Mods Must Be Implemented Per NRC 790507 Order.Certificate of Svc Encl Project stage: Request ML19247B2361979-07-23023 July 1979 Requests Addl Info Re Degraded Grid Voltages.Requests Response within 45 Days Project stage: Other ML19250A5241979-10-15015 October 1979 Notifies of Invalidity of 770603 & 760917 Submittals Re Degraded Voltage Susceptability.Fire Protection & TMI-related Mods to 230 Kv Transmission Sys Necessitate Redesign of Safety Grade Onsite Distribution Sys Project stage: Other ML19250A5281979-10-15015 October 1979 Requests Extension to 791018 for Response to . Delay Caused by Need to Modify Min Expected Voltage Assumptions & Perform re-analysis Project stage: Other ML19254D6491979-10-16016 October 1979 Responds to 790921 Request for Review of Unnecessary Challenges to Reactor Trip & Safeguard Sys.Forwards to NRC Re Review Project stage: Request IR 05000312/19790211979-10-17017 October 1979 IE Insp Rept 50-312/79-21 on 790904-28.Noncompliance Noted: Physical Security Project stage: Request ML19253B8121979-10-17017 October 1979 Forwards Response to NRC 790808 Request for Verification of Adequacy of Offsite Power Sys & Onsite Electrical Distribution Sys.Existing Sys Will Be Adequate W/Normal Plant Lineup After Implementation of Mods Project stage: Request ML19210C1191979-11-0202 November 1979 RO 79-13:on 790808,reanalysis of Switchyard Voltage Indicated That Present Setpoint for Bus Unloading Is Insufficient to Prevent Nuclear Svcs Busses from Decreasing Below 75% Rated Voltage.Undervoltage Relay Changed Project stage: Other ML19210E3901979-11-26026 November 1979 Submits Followup Request for Extension from 791105 to 791117 for Completion of Mods Re Degraded Voltage Conditions Project stage: Request ML19260C1261979-12-0606 December 1979 Corrects Util Re Max Experience Switchyard Voltage.District Changed Setpoint of Existing Overvoltage to 241 Kv During 791117 Outage.Operation at 241 Kv Acceptable Project stage: Other ML19260C8781980-01-24024 January 1980 Submits Clarification of Util Status on Degraded Voltage Mods.Will Submit Second Level Coincident Logic Design W/ Required Supporting Analysis & Documentation for Review, Comment & Approval by 800303 Project stage: Other ML19305D7101980-04-0808 April 1980 Responds to NRC Request for Info to Suppl 791017 Response to NRC Re Grid Voltage Degradation.Info Will Be Submitted by 800425 Project stage: Request ML19330B6701980-08-0101 August 1980 Forwards Revised Response to Inquiry on Adequacy of Facility Safety Grade Electrical Distribution Sys Voltage Since Condition Discovered at Millstone Unit 2.Util Is Planning to Implement Mod to Sys During 810601 Refueling Outage Project stage: Other ML19332A7331980-09-0303 September 1980 Requests Addl Info Re Adequacy of Station Electrical Distribution Sys Voltage Project stage: Other ML19337A6271980-09-22022 September 1980 Forwards Response to NRC 800903 Request for Info Re Adequacy of Station Electrical Distribution Sys Voltage Project stage: Request ML19337A6321980-09-22022 September 1980 Safety Evaluation & Statement of Staff Positions Relative to Emergency Power Sys for Operating Reactors Project stage: Other ML19305F2481980-12-0404 December 1980 Safety Evaluation Re Degraded Grid Voltage Protection for Class IE Power Sys at Facility.Proposed Design Mods & Changes to Tech Specs Are Acceptable Project stage: Approval ML19345F3691981-02-0202 February 1981 Application for Proposed Amend 51,Revision 1,to Ol.Forwards Proposed Tech Spec Changes.Changes Include All Items Submitted in Proposed Amend 51 Submitted on 780620 & Revisions Agreed to by Project stage: Request ML19345F3751981-02-0202 February 1981 Tech Spec Pages 4-34,4-34a,4-7b,3-41,3-42,3-43,3-44,3-41a & 3-41b Re Emergency Power Sys Periodic Testing & Auxiliary Electrical Sys Project stage: Other 1979-11-26
[Table View] |
Text
7EQ 9
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I UNITED STATES OF AMERICA A
p NUCLEAR REGULATORY COMMISSION E
g In the Matter of:
)
)
SACRAMENTO MUNICIPAL UTILITY DISTRICT
)
Docket No. 50-312
)
Rancho Seco Nuclear Generating Station
)
CONTENTIONS IN SUPPORT OF REQUEST FOR HEARING CONTENTIONS:
1.
Rancho Seco Nuclear Generating Station is unsafe with respect to the health and safety of myself and other members of the public who reside or work in the vicinity of Rancho Seco Nuclear facility.
A.
Babcock and Wilcox reactors are too susceptible to feed-water transients which may result in an accident.
B.
Rancho Seco does not have an adequate evacuation plan.
C.
Rancho Seco has inadequate radiation monitoring devices.
D.
Rancho Seco has inadequate notification procedures for informing local authorities in case of a potential accident.
E.
Rancho Seco does not have a recombiner.
F.
The present elevat. ion of the steam generator is a design defect.
G.
Pressuriner, steam generator, vessel and plumbing arrangements are improperly designed with respect to bubble formation in hydraulic high points.
H.
Babcock and Wilecx's once through steam generator level measurement is a design deficiency.
I.
Feedwater systems and auxilary feedwater systems are too scept b1 to ccamon-mode failures.
7909260i11 J.
Sabcock and Wilcox' pressur'fzer tank and quench tank 8
1 n i r; inn
s E00R ORIGlWL sizes are too small.
K.
Babcock and W11cox's primary loop arrangement is defectively designed with respect to steam bindings, steam bubble formation, and pump cavitation.
L.
Operator data on pressurizer level / vessel level are unreliable and can be mislead.ing during an accident.
M.
Inability to isolate steam generator B under some circumstances.
N.
Inadequate reliability of off-site power.
O.
Problems with relief valves sticking open.
P.
Ins uf ficient instrumentation and data for post-accident monitoring.
Q.
Inadequate level instruments.
R.
Insuf ficient analysis between what functions should be hard equipment responsibilities and what can be a soft procedural function.
S.
Inadequate control room design.
T.
Question of competence of plant personnel and management to operate Rancho Seco.
2.
Sufficient modificati.ons have not been made in light of the experience at Three Mile Island Unit No. 2 to allow the Rancho Seco facility to operate in a safe manner.
A.
In support of this contention and incorporated herein by this reference I refer to communications to NRC from the ACRS regarding TMI since March 28, 1979 which state specific recom-mendations which have not been adequately addressed.
1015 101 t
i0
\\
3.
Failure of the NRC Commission to act quickly and decisively during the TMI-2 accident and the absence of any assurance that the exercise of their regulatory authority wculd be adequate in a second TMI-2 type or similar accident.
C.
Adequacy of training requirements and job descriptions of plant operators and associated personnel.
3 The long-term modifications referred to in the May 7, 1979 order of the NRC must be implemented before the Rancho Seco Nuclear facility can operate l'n a safe manner.
CONCLUSION We request that the Nuclear Regulatory Commission address these contentions and provide for the suspension of operation of the Rancho Seco Nuclear Generating Plant, unless they or their designated representatives publicly conclude that, in light of the accident at TMI-2, the Rancho Seco Nuclear Generating Plant can continue to be operated without endangering the health, safety and econc.nic well being of the Petitioners and the people of Sacramento.
Submitted,
/
\\/
GARY HURSH /
.r/ -
, hhh' - l b
( "N1If RICHARD D.
saSTRO Members Board of Directors, Sacramento Municipal Utility Dictrict f0,I 1015 102
r P00R BRIGM-UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION In the Matter of SACRAMENTO MUNICIAAL UTILITY
)
Docket No.
50 - 312 OISTRICT
)
)
Rancho Seco Nuclear Generating
)
Sta tion
)
I hereby certify that copies of" CONTENTIONS IN SUPPORT OF REQUEST FOR HEARING" in the above captioned proceeding have been served cn the following by deposit in the United States mail, first class, this 23rd day of July,1979, and that one copy was delivered by hand to the office of the Nuclear Regulatory Comission in Washington,D.C. on this same day:
DAVID F.
EAP LAI:, Esq.
LEONARD BICKWIT, Esq.
Secrc:ar, General Councel General Counsel c.
P O b o:- 15E30 U.S.
Nuclear Regulator Commission Sacramentc, CA 95E13 Washington, D.C.
20555 TI CTHY
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DILLDI:, Lug.
ATDMIC SAFETY AND LICENSING Sultu 3M BOARD PANEL
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1S50 K Street, I4. K.
U.S.
Nuclear Regulatory Commission
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D.C.
.000t Washington, D.C.
20555 MR.
RICliARD D.
CASTRU ATDMIC SAFETY & LICENSING MR GARY HURSH APPCAL BOARD PANEL facramento Municipsi l'tiliry U.S.
' uclear Regulatory -Commission cir ric:
Washington, D.C.
20555 C201 S E t reet-P O b o :- 15830 Fucrament, CA 95S17 MR. SAMUEL J.
CHILK Secretary of the Commission Mi'
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V.::DERVELCE:,
U.S.
Nuclear Regulatory Commission
' O A:- REISS Washington, D.C.
20555
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P OT:E 7 I C H P I S T O P lie ! W O :
'r:endc ci the Carth DOCKETING AND SERVICE SECTION c 111. c uc a Legisl :ti ve G fi ce Office of the Secretary 717 - Strcot, S ui t.e 2 0 B U.S.
Nuclear Regulatory Commission Sacr _mentc, CA 9581:
Washington, D.C.
20555
'Y i.vh RICHARD D. CASTRO, PETITIONER 2015 21st Street
. Sacramento, CA 95816-
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