Letter Sequence Request |
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MONTHYEARML19254F2741979-11-0101 November 1979
Requests Extension on Tech Spec Surveillance Interval for Reactor Vessel Internal Vent Valves
Project stage: Other
ML20002D6321981-01-14014 January 1981
Forwards Addl Safety Analysis Justifying Tech Spec Change Request 90,modifying Reactor Vessel Internal Vent Valve Surveillance to Permit Cycle 5 Operation W/O Repeating of Surveillance
Project stage: Other
ML19350A7251981-03-11011 March 1981
Submits Further Justification for Tech Specs Change Request 90 Re Reactor Vessel Internal Vent Valves.Change Requested Mod to Permit Cycle 5 Operation W/O Reperformance of Surveillance
Project stage: Other
ML20133M5451985-10-18018 October 1985
Application for Amend to License DPR-54,consisting of Proposed Amend 138,changing Offsite & Onsite Organization Charts.Fee Paid
Project stage: Request
ML20133M5531985-10-18018 October 1985
Proposed Tech Specs,Changing Offsite & Onsite Organization Charts
Project stage: Other
ML20205E9921986-08-12012 August 1986
Proposed Tech Specs,Changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Shift Crew Personnel Complement for Compliance w/10CFR50.54(m)(2)(i)
Project stage: Other
ML20205E9791986-08-12012 August 1986
Application for Rev 1 to Proposed Amend 138 to License DPR-54,changing Corporate Organizations That Provide Support to Nuclear Safety & Revising Complement of Shift Crew Personnel for Compliance w/10CFR50.54(m)(2)(i)
Project stage: Request
ML20215A9091986-09-22022 September 1986
Application for Proposed Amend 145 to License DPR-54, Revising Tech Specs to Make Wording Consistent W/Sts & to Extend Waiver on Surveillance of Internal Vent Valves to Cycle 8 Refueling.Fee Paid
Project stage: Request
ML20215A9291986-09-22022 September 1986
Proposed Tech Specs Making Wording Consistent W/Sts & Extending Waiver on Surveillance of Internal Vent Valves to Cycle 8 Refueling
Project stage: Other
ML20211E9231986-10-17017 October 1986
Forwards Updated Interim Organizational Charts for Nuclear Restart Implementation & Nuclear Plant Dept & Tabular Listing of Interim Corporate & Onsite Positions as Compared to Tech Spec Figures 6.2-1 & 6.2-2
Project stage: Other
ML20212E4931986-12-17017 December 1986
Smud Vent Valve Matl & Hinge Clearances
Project stage: Other
ML20212E5351987-01-29029 January 1987
Matls-Chemistry Assessment for Internal Vent Valve
Project stage: Other
ML20211B2701987-02-11011 February 1987
Forwards Target Nuclear Organization for Restart (Transition Plan) for Review.Plan Provided to Facilitate Transition from Interim (Prestart) to Ultimate Nuclear Organization. Organizational Chart,Resumes & Position Descriptions Encl
Project stage: Other
ML20212E4761987-02-20020 February 1987
Forwards B&W Documents 51-1167259-00, Smud Vent Valves Matl & Hinge Clearances & 51-1167330-00, Matls-Chemistry Assessment for Internal Vent Valves, in Response to G Kalman Request Re Proposed Amend 145 to License DPR-54
Project stage: Other
ML20234D6591987-09-16016 September 1987
Proposed Tech Specs,Reflecting Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function
Project stage: Other
ML20195G4201987-09-16016 September 1987
Rev 2 to Proposed Amend 138,revising Tech Specs to Reflect Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function
Project stage: Other
ML20236K3761987-11-0202 November 1987
Application for Amend to License DPR-54,consisting of Proposed Amend 138,Rev 2,Suppl 1,adding non-licensed Personnel to Tech Spec Table 6.2-1,limited Representation to Tech Spec 6.5.2.5 & LERs to Tech Spec 6.5.2.6
Project stage: Request
ML20236K3921987-11-0202 November 1987
Proposed Tech Spec Table 6.2-1, Shift Crew Personnel & License Requirements & Pages 6-7 & 6-8,adding non-licensed Personnel,Statement Re Limiting Representation to Minority of Quorom & Lers,Respectively
Project stage: Other
ML20236U3361987-11-25025 November 1987
Proposed Tech Specs Page 1-2b,adding Words to Effect That 3.25 Factor Applicable to Three Consecutive Time Intervals Will Be Reset to Begin After Next Surveillance
Project stage: Other
ML20236U3241987-11-25025 November 1987
Suppl 1 to 860922 Application for Amend to License DPR-54, Consisting of Proposed Amend 145,adding Wording to Tech Spec Page 1-2b Re Surveillance of Internal Vent Valves to Cycle 8 Refueling Outage
Project stage: Request
ML20236V5821987-11-25025 November 1987
Application for Amend to License DPR-54,consisting of Suppl 2 to Rev 2 to Proposed Amend 138,changing Tech Spec Figures 6.2-1 & 6.2-2 to Assign Nuclear Security Manager & Staff Directly to Nuclear Power Production
Project stage: Request
ML20236V7961987-11-25025 November 1987
Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively
Project stage: Other
ML20237B3961987-12-0707 December 1987
Forwards Amend 92 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Redefine Refueling Interval to Make Definition Consistent W/Sts & Extends Surveillance Interval of Vent Valves to Cycle 8 Refueling
Project stage: Approval
ML20149E5881988-01-0606 January 1988
Supplemental Application for Amend to License DPR-54, Consolidating Applicability Requirement for Containment Integrity in Tech Spec 3.6 Applicability Statement
Project stage: Supplement
ML20149E5971988-01-0606 January 1988
Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement
Project stage: Other
ML20196B7981988-02-0101 February 1988
Application for Proposed Amend 138 to License DPR-54.Amend Revises Nuclear Organization Chart,Figure 6.2-2 as Listed
Project stage: Request
ML20196B8071988-02-0101 February 1988
Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart
Project stage: Other
ML20246M1741989-05-0808 May 1989
Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted
Project stage: Approval
1987-01-29
[Table View] |
Text
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O g'"SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT D P. O. Box 15830, Sacramento CA 95852-1830 (916) 452-3211
=
AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA I
NOV 2 51971 AGM/NPP 87-408 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.
Associate Director for Projects Philips Bldg.
7920 Norfolk Averme Bethesda, MD 20014 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION I
LICENSE NO. OPR-54 l
PROPOSED AMENDMENT 138, REVISION 2, SUPPLEMENT 2
Dear Mr. Miraglia:
This second supplement to Proposed Amendment No.138, Revision 2 further enhances the Rancho Seco organization by assigning a Manager, Nuclear Security and his staff directly to the AGM, Nuclear Power Production.
Previous to this Supplement 2, Nuclear Security was matrixed to the AGM, Nuclear Power i
Production from the headquarters organization.
This supplement affects the following three pages of Proposed Amendment No.
138, Revision 2, submitted September 16, 1987:
1, Attachment I, paga 1, reply to NRC's request (1.b.) for additional information.
2.
Technical Specification Figure 6.2-1, page 6-2a, SMUD CORPORATE SUPPORT OF NUCLEAR SAFETY TO RANCHO SECO.
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3.
Technical Specification Figure 6.2-2, page 6-2b, Nuclear Organization Chart.
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The revised pages are enclosed with this letter. The Safety Analysis and No Significant Hazards Consideration in the District's September 16, 1987 submittal of Propos:ed Amendment No.138, Revision 2, are not changed or affected by this supplement.
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PDR ADOCK 05000312 k
p PDR RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Ci ies Road, Herald, CA 95638-9799;(209) 333 2935
.-AGM/NPF87-408-Frank J. Miraglia, Jr. - NOV 2.51987 Please contact me if you have any questions. Members of your staff with questions requiring additional *nfomation.or. clarification may contact Mr. Vern Grayhek at (209) 333-2935, extension 4916..
Si erely
[ sep h. f, h
_0 Firlit Assistant General Manager, Nuclear Power Production
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s Sworn to and subscribed before me this g25 day of November 1987.
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yotary Public gp u acu,LstAL- ~l Attachments
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- w. memo ccumv cc:
G. Kalman, NRC, Bethesda A. D'Angelo, NRC, Rancho Seco.
J. B. Martin, NRC, Walnut Creek i
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- ATTACHMENT It SUBMITTAL OF REQUIRED INFORMATION PAGE 1 0F 2 Following are the District's replies.t'o NRC's' request of January 15, 1987, for additional information concerning Section'6, Administrative Controls, of the Rancho Seco Technical Specifications.
For the convenience of the reviewers, the NRC inquiry is presented before'each District. reply:
1.
Fiaure 6.2-1 a.
Hith respect to each of the functional units under the Chief Executive Officer, Nuclear, provide a description of their function and responsibilities.
Reply The position descriptions of each manager of the. functional units under the Chief-Executive Officer, Nuclear, were submitted to the NRC on February 11, 1987, as Attachment C.
These position descriptions include details of unit function and responsibility, b.
Is the responsibility for the Rancho Seco Security Program under the block " Security" that reports to the AGM, Administration and Services?
If not, who has responsibility for that function?
Bfply The responsibility for the Rancho Seco Security Plan is under the
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Manager, Nuclear Security, reportable to the AGM, Nuclear Power Production, (see Figure 6.2-2 in Attachment III).
c.
You state that the AGM, Engineering is not responsible for Nuclear
)
Engineering.
Does the AGM, Engineering have any responsibility.for
'j engineering associated with Rancho Seco Nuclear Generating Station, Unit No. l?
Reply Engineering associated with Rancho Seco is provided by the Nuclear Engineering Department and by system engineers in the Plant Performance Department (see Figure 6.2-2 in Attachment III).
Both of these departments are located on site.
The AGM, Engineering and Production l
in the District headquarters office has no responsibility for Rancho Seco engineering.
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