ML20236W867
Letter Sequence Other | |
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TAC:65256, (Approved, Closed) | |
Questions
Results Other: ML20147F043, ML20147F077, ML20149G178, ML20151B320, ML20196B876, ML20234C601, ML20235Q511, ML20236U082, ML20236W867 | |
MONTHYEARML20210B4921987-04-30030 April 1987
[Table View]Informs That Region V Will Provide Detailed Contractor Review of Facility Tech Specs for Errors,Omissions & Ambiguities,Per Discussion at 870428 Meeting.Recommends That Util Review Rept for Addl Changes to Tech Specs Project stage: Meeting ML20215L3041987-06-22022 June 1987 Summary of Meeting W/Util & NUS on 870611 in Bethesda,Md Re Adequacy of Tech Specs.List of Attendees,Viewgraphs & Candidate Tech Specs for Consideration During Finalization of Program Encl Project stage: Meeting ML20236C4011987-07-22022 July 1987 Discusses Schedule for License Changes,Based on NRC 870430 Tech Spec Evaluation Rept.Understands from 870611 Meeting That Items Not Yet Approved by NRC as License Amends Shall Be Procedurally Implemented Prior to Facility Startup Project stage: Meeting ML20234C6011987-09-0808 September 1987 Discusses Status of 870722 License Changes Based on NRC Tech Spec Evaluation Rept.Proposed Amend 164 Incorporates 19 Items Scheduled for Submittal by 870930.Remaining 33 Concerns Under Evaluation.Resolution Expected by 871029 Project stage: Other ML20235Q4781987-10-0101 October 1987 Application for Proposed Amend 164 to License DPR-54, Consisting of Enhancements to Tech Specs to Resolve Certain Comments Resulting from NRC Region V Feb & Mar 1987 Contracted Comparison of Plant Tech Specs to Sts.Fee Paid Project stage: Request ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS Project stage: Other ML20236G6421987-10-28028 October 1987 Forwards Response to 34 NRC Concerns Identified in 870611 Meeting in Bethesda,Md Re Tech Spec Evaluation Rept Concerning Proposed Amend 164.Proposed Changes Will Be Procedurally Implemented Prior to Plant Restart Project stage: Meeting ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 Project stage: Other ML20236U0681987-11-25025 November 1987 Suppl 1 to Rev 0 to 871001 Application for Amend to License DPR-54,consisting of Proposed Amend 164.Attachment 1 Consists of Response to NRC Questions & Comments on Subj Proposed Amend & Util 871028 Responses to 34 Concerns Project stage: Request ML20236W8671987-12-0303 December 1987 Proposed Tech Spec,Combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water Project stage: Other ML20236W8581987-12-0303 December 1987 Application for Amend to License DPR-54,consisting of Rev 0, Suppl 2 to Proposed Amend 164,combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water.Revised Tech Spec Page 3-21 Encl Project stage: Request ML20149G1611988-02-0808 February 1988 Application for Amend to License DPR-54,consisting of Rev 0, Suppl 4 to Proposed Amend 164,adding Note to Tech Spec 3.3 to Eliminate Conflict W/Tech Spec 3.2.2.2 Project stage: Request ML20196B8761988-02-0808 February 1988 Provides Commitment Not to Use Two Pump Option During Startup Through Power Operation.Commitment Will Be Implemented Administratively & Procedurally Prior to Startup from Current Outage Project stage: Other ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys Project stage: Other ML20147F0431988-02-25025 February 1988 Forwards Suppl 5 to Rev 0 to Proposed Amend 164 to License DPR-54,revising Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2 to Require That Surveillances Be Performed Only When Gaseous Chlorine Onsite,Per NRC Request Project stage: Other ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite Project stage: Other ML20153B2671988-03-15015 March 1988 Forwards Amend 97 to License DPR-54 & Safety Evaluation. Amend Modifies Various Sections of Tech Specs to More Closely Resemble B&W STS 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 1987-06-22 |
ML20236W867 | |
Person / Time | |
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Site: | Rancho Seco |
Issue date: | 12/03/1987 |
From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
To: | |
Shared Package | |
ML20236W860 | List: |
References | |
TAC-65256, NUDOCS 8712080280 | |
Download: ML20236W867 (1) | |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20059C1861993-12-22022 December 1993
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Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20149K8621988-02-12012 February 1988 Proposed Tech 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[Table view]Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear 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164~ . 'l RANCHO SECO UNIT 1 I TECHNICAL SPECIFICATIONS l Limiting Conditions for Operation E.: Two independent Nuclear. Service Water subsystems shall be OPERABLE with each subsystem comprised of:
- 1. One OPERABLE Nuclear Service Cooling _ Hater (NSCH) loop.
2.. One OPERABLE Nuclear Service Raw Hater (NSRW) loop.
- 3. One OPERABLE Nuclear Service Spray Pond with:
- a. A' minimum water level of 5'4",'and
- b. A maximum water temperature of 95'F.
. Action Hith one Nuclear Service Hater subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT. SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTD0hN :
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- F. Safety features valves and interlocks associated with each of the above systems are operable. Inoperable valves shall be.
placed in the saf?ety features position.
164-~ 3.3.2 .During power operation, hot standby, hot shutdown or startup conditions, the primary coolant system pressure isolation valves shall be functional hs follows:
- 1. All pressure isolation-valves listed in Table 3.3-1 shall be functional as a pressure isolation device, except as specified 164-- in 3.3.2.2. Valve leakage shall not exceed the amounts indicated.
- 2. In the event that integrity of any pressure isolation valve specified in Table 3.3-1 cannot be deinonstrated, reactor operation may continue, provided that at least two valves in each high pressure line having a non-functional valve are in i and remain 10 the mode corresponding to the isolated condition.(a>
164~- 3. If Specifications 3.3.2.1 and 3.3.2.2 cannot be met, a shutdown shall be initiated, the reactor shall not remain critical and shall be brought to a cold shutdown condition within an I additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 8712080280 871203 PDR ADOCK0500g2 P
i Proposed Amendment 164 3-21
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