Letter Sequence Request |
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Results
Other: ML20147C490, ML20149E859, ML20151B320, ML20155D675, ML20197B030, ML20199B161, ML20204F596, ML20210R060, ML20211B406, ML20211B442, ML20212H574, ML20212H582, ML20214E205, ML20214L960, ML20215H383, ML20215H397, ML20234F422, ML20235R405, ML20235R426, ML20236D305, ML20236D319, ML20236P920, ML20245E060, ML20245E067
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MONTHYEARML20155D6751985-12-31031 December 1985
Annual Nonradiological Environ Monitoring Rept,1985
Project stage: Other
ML20211B4421985-12-31031 December 1985
Annual Radiological Environ Operating Rept for 1985
Project stage: Other
ML20210R0601986-02-24024 February 1986
Staff Assessment of Environ Radioactive Contamination in Vicinity of Rancho Seco Nuclear Power Plant
Project stage: Other
ML20214E2051986-03-0303 March 1986
Forwards Semiannual Radioactive Effluent Release Rept,Jul- Dec 1985. Changes to Offsite Dose Calculation Manual, Process Control Program & Rept Corrections Included. Operational & environmentally-related Events Discussed
Project stage: Other
ML20214L9801986-04-0101 April 1986
Summary of 860325 Meeting W/Epa Re Offsite Contamination Problems & Requirements of 40CFR190
Project stage: Meeting
ML20197B0301986-04-30030 April 1986
Informs That Util Will Submit Completed 1985 Annual Radiological Environ Operating Rept by 860530.Delay Due to Difficulties in Completing Liquid Effluent Pathway Land Use Census
Project stage: Other
ML20211B4061986-05-27027 May 1986
Forwards 1985 Annual Radiological Environ Operating Rept, Including Parts I & II of Environ Radiological Studies Downstream from Rancho Seco Nuclear Power Generating Station - 1985
Project stage: Other
ML20199B1611986-06-0505 June 1986
Special Rept 86-08 Re Max Hypothetically Exposed Individual Surpassing Numerical Guides for Design Objectives of 10CFR50,App I.More Appropriate Modeling Techniques Encl. Offsite Dose Calculation Manual Revised
Project stage: Other
ML20204F5961986-07-0303 July 1986
Responds to NRC Re Violation Noted in Insp Rept 50-312/86-15.Corrective Actions:Util Will Submit Amend to Tech Spec Table 4.21-1 Re Radioactive Liquid Waste Sampling Prior to Startup
Project stage: Other
IR 05000312/19860231986-07-18018 July 1986
Enforcement Conference Rept 50-312/86-23 on 860620.Major Areas Discussed:Violation Noted During Insps of Emergency Preparedness Program & Radioactive Effluent Mgt (Insp Repts 50-312/86-14 & 50-312/86-15)
Project stage: Request
ML20212G1351986-07-22022 July 1986
Advises That Changes to Radiological Effluent Tech Specs Should Be Proposed to Eliminate Possibility of Unacceptable Radiation Levels in Liquid Effluents.Evaluation of 860224 Rept Encl.Meeting Requested
Project stage: Meeting
ML20214L9601986-08-29029 August 1986
Forwards Documentation Summarizing NRC Actions to Close Out Offsite Contamination Issue,In Response to 860325 Request
Project stage: Other
ML20055C2251986-09-30030 September 1986
Responds to NRC 860718 Request for Addl Info Re Plant Liquid Effluents.Requested Info Will Be Provided by End of Nov 1986 Due to Magnitude of Effort Required
Project stage: Request
ML20245E0671986-12-0202 December 1986
Forwards Util Response to 860718 Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Util Considers That Discharge of Radioactive Matl in Liquid Effluents Allowable by Tech Specs within Limits of 10CFR20,App B
Project stage: Other
ML20245E0601987-01-0505 January 1987
Forwards Revs to Util 861202 Response to NRC Liquid Effluent Inquiry for Clarification,Per 861222 Discussion W/R Meeks
Project stage: Other
ML20212H5821987-01-12012 January 1987
Radiological Effluent Release & Radiological Environ Operating Repts for 1984,Rancho Seco Nuclear Generating Station, Technical Evaluation Rept
Project stage: Other
ML20212H5741987-01-16016 January 1987
Forwards TER-C5506-657, Radiological Effluent Release & Radiological Environ Monitoring Operating Repts for 1984, Rancho Seco Nuclear Generating Station, Technical Evaluation Rept
Project stage: Other
ML20245E0631987-02-19019 February 1987
Forwards Response to NRC 861224 Request for Addl Info Re Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Response Completes Util Efforts to Provide Requested Info
Project stage: Request
ML20205S8181987-02-25025 February 1987
Notification of 870303 Meeting W/Util in Bethesda,Md to Review Discrepancies in Plant Liquid Effluent Program & to Discuss Changes to Tech Specs & Offsite Dose Calculation Manual to Correct Identified Discrepancies
Project stage: Meeting
ML20197D4831987-04-0707 April 1987
Summary of 870303 Meeting W/Util in Bethesda,Md Re Problems Identified W/Facility Liquid Effluent Program & Proposed Corrective Actions.Attendance List Encl
Project stage: Meeting
ML20215H3831987-04-15015 April 1987
Forwards Rev 1 to Procedure R-0775, Facility Change Safety Analysis. Design Bases of Current Mod to Secondary Waste Water Sys Not Intended to Be Equivalent to Evaporation Ponds Described in Submittal
Project stage: Other
ML20215H3971987-04-15015 April 1987
Rev 1 to Procedure R-0775, Facility Change Safety Analysis
Project stage: Other
ML20209C7401987-04-20020 April 1987
Confirms Commitments Made During 870303 Meeting W/Nrc in Bethesda,Md Re Radiological Liquid Effluent Matters.Dose Based Surveillance Std Appropriate for Ensuring Compliance w/10CFR50,App I Regulation.List of Commitments Encl
Project stage: Meeting
ML20235F7541987-06-30030 June 1987
Application for Amend to License DPR-54,consisting of Amend 155,revising Tech Specs Re Radiological Effluents to Ensure Compliance W/Regulatory Requirements Concerning Effluent Monitoring & Nearby Land Use Identification.Fee Paid
Project stage: Request
ML20235R4051987-10-0303 October 1987
Rev 1 to Proposed Amend 155,revising Radiological Effluent Tech Specs to Incorporate Clarifications & Correct Editorial Errors
Project stage: Other
ML20235R4261987-10-0303 October 1987
Proposed Radiological Effluent Tech Specs,Incorporating Clarifications & Correcting Editorial Errors
Project stage: Other
ML20236D3191987-10-0707 October 1987
Rev 0 to Radiological Environ Monitoring Program Manual
Project stage: Other
ML20236D3051987-10-20020 October 1987
Forwards Rev 0 to Radiological Environ Monitoring Program Manual, for Review in Support Evaluation of Proposed Amend 155 to License DPR-54
Project stage: Other
ML20236P9201987-11-12012 November 1987
Forwards Radioactive Liquid Effluent Sys Description Including P&Id,Design Criteria,Instrumentation & Control Measures to Support Evaluation of Proposed Amend 155
Project stage: Other
ML20149E8591987-12-22022 December 1987
Proposed Tech Specs,Establishing New Set Lower Limits of Detection for Prebatch Release & Composite post-release Analyses
Project stage: Other
ML20149E8521987-12-23023 December 1987
Supplemental Application for Amend to License DPR-54, Consisting of Rev 2 to Proposed Amend 155,establishing New Set of Lower Limits of Detection for Prebatch Release & Composite post-release Analyses
Project stage: Supplement
ML20234F4221987-12-27027 December 1987
Forwards Rev 5 to AP.310, Offsite Dose Calculation Manual, for Review to Support Evaluation of Proposed Amend 155, Rev 2.Rev Incorporates Results of Verification & Validation as Well as NRC & Internal Reviews
Project stage: Other
ML20147C4901988-01-0505 January 1988
Forwards Fr Notice of Consideration of Issuance of Amend to License DPR-54 & Proposed NSHC & Opportunity for Hearing on 870630 Request Re Revs to Radiological Effluent Tech Specs
Project stage: Other
ML20149E2561988-01-0707 January 1988
Forwards Supplemental Info to Radioactive Liquid Effluent Sys Description Provided Via Ltr Gca 87-763 Dtd 871112,to Support Evaluation of Rev 2 to Proposed Amend 155.Concerns Raised Re Radioactive Liquid Effluent Sys Listed
Project stage: Supplement
ML20148J8111988-03-17017 March 1988
Forwards Amend 98 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs,Reducing Lower Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys
Project stage: Approval
ML20151B3201988-03-30030 March 1988
Forwards Errata to Amends 97 & 98 to License DPR-54, Correcting Inadvertent Errors in Tech Specs
Project stage: Other
1987-10-20
[Table View] |
Text
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I g~^;SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA GCA 87-192 QUN 3 01987 U. S. Nuclear Regulatory Commission Attn:
Frank J. Miraglia, Jr.
Associate Director for Projects n
Philips Building 7920 Norfolk Avenue Bethesda, MD 20014 DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION i
LICENSE NO. DPR-54 PROPOSED AMENDMENT NO. 155 l
Dear Mr. Miraglia:
In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District hereby submits Proposed Amendment No.155 to Operating License No. DRP-54 for Rancho Seco Nuclear Generating Station Unit No. 1.
Proposed Amendment No. 155 consists of changes and additions to the Rancho Seco Technical Specifications regarding radiological effluents to ensure compliance with regulatory requirements as they pertain to effluent monitoring, nearby land use identification, offsite dose calculations, environmental monitoring and limitations on calculated offsite doses.
Since Proposed Amendment No. 138 represents a substantial change to Section 6 of the Technical Specifications, Proposed Amendment No.155 changes to Section 6 are incorporated with the latest draft of Proposed Amendment No.
138, Revision 2 for clarity and uniformity of review.
Proposed Amendment No.
155 will be revised to reflect any changes when Proposed Amendment No. 138, Revision 2 is submitted.
h provides the Description of the Proposed Change, the associated CT Safety Analysis, and the "No Significant Hazards Determination." Attachment 2 h
provides the proposed Technical Specifications.
Mmo Pursuant to 10 CFR 50.91(b)(1), the Radiological Health Branch of the ps:
California State Department of Health Services has been informed of this g83 proposed amendment by copy of this submittal.
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.y RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
GCA 87-192-
. Frank J. Miraglia f)UN 3 01987 I
Enclosed is a check in the amount of $150.00 as required by 10 CFR 170.21,
" Schedule of Fees."
If there are any questions concerning this report, please contact Mr. Ron H. Colombo at (916) 452-3211, extension 4236.
Sincerely, l(
ff/
J@
. Carl Andog ni Chief Executive Officer, Nuclear Sworn to and subscribed before me this O k day of June,1987.
SY Y//cYls Notary Public / '
Attachments OFFICIAL SEAL
}/
ESTHER H. HUGHES I
2
. NOTARY PUBLLC-CALFORNIA SACRAMENTO COUNTY cc w/atch:
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My comm. spirn oct 21,1989 a n_~~_
G. Kalman, NRC, Bethesda (2)
A. D'Angelo, NRC, Rancho Seco J. B. Martin (2)
MIPC (2)
INP0
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GENERAL ACKNOWLEDGMENT No so State of
/A 2
On this thOk day of 92M-19k, before me, County of 92*A nLAD 22
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the undersigned Notary Public, personally appeared
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OFFICIAL SEAL
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O personally known to me i NOTARY Pu L 5-C o NIA m
subscribed to the SACRAM:NTo nouNTv r'
to be the person (s) whose name(s)
My Comm. Expres Oct 21,1989 within instrument, and acknowledged that,A executed it, 1
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WITNESS my hand and official seal.
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7110 122 NATIONAL NOTARY ASSOCIATION. 23012 Ventors BNd
ATTACHMENT I SAFETY ANALYSIS OF PROPOSED AMENDMENT NO. 155
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1 FACILITY CHANGE SAFETY ANALYSIS LOG NO. 921 PROPOSED AMENDMENT NO. 155 PAGE 1 i
DESCRIPTION:
Proposed Amendment 155 consists of changes and additions to the Rancho Seco I
Technical Specifications regarding radiological effluents to ensure compliance with the requirements of 10 CFR 50, Appendix I, as it pertains to effluent monitoring, nearby land use identification, offsite dose calculations, environmental monitoring and limitations on calculated offsite doses.
l RFASON FOR CHANGE:
The amendment proposed in this safety analysis are a result cf conclusions documented in a July 22,1986, " Staff Evaluation of Rancho Seco Radiological Effluent Technical Specifications and Offsite Dose Calculation Manual Regarding Offsite Doses From Liquid Effluent." This document noted that radionuclides concentrations near the Rancho Seco site resulting from the release of liquid effluents were found to be at levels which could cause the maximum - exposed individual to receive doses well in excess of the dose limits set forth in the 10 CFR 50, Appendix I and 40 CFR 190. Specifically, as a result of the NRC' review, an inconsistency was found between the Lower Limit of Detection (LLD) listed in Table 4.21-1 of the Rancho Seco Technical Specification Surveillance Standards (Section 4.21.1) and Technical Specification Sections (3.17.2 and 4.21.2) relating to 10 CFR 50 Appendix I design objectives. Additional NBC citings for nonconformance to 10 CFR 50 Appendix I were documented in an WRC Region V Inspection Report 86-15 sent'to the District on June 6, 1986. District response to the citings on July 3, 1986 include commitments to submit Technical Spe'cification revisions for conformance with the requirements of 10 CFR 50 Appendix 1.
The commitments are addressed in the Proposed Technical Specification Amendment No.155.
EVALUATION AND BASIS FOR SAFETY FINDINGS The following is a discussion of each Technical Specification change. The changes include administrative changes, changes in accordance with the design basis for Rancho Seco and changes that represent additions or upgrade to existing surveillance requirements and limitations. The Tech Spec changes listed in this analysis will be formatted by individual tech spec changes, accompanied by the existing specification, and a discussion of the change. A safety analyais and a no significant hazards consideration will also be included with each change. In addition, attached are copies of the Proposed Amendment No. 155 of the Technical Specifications.
4