ML20199E224
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Letter Sequence Other | |
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Administration | |
MONTHYEARML20199B2901986-06-13013 June 1986
[Table View]Proposed Tech Spec 4.8.1A,incorporating Proposed Amend 148, Permitting Sys Testing of Auxiliary Feedwater Pump Under Conditions of Power Operation or Plant Shutdown Project stage: Other ML20199B2721986-06-13013 June 1986 Application for Amend to License DPR-54,incorporating Proposed Amend 148,revising Tech Spec 4.8.1A to Permit Sys Testing of Auxiliary Feedwater Pump Under Conditions of Power Operation or Plant Shutdown.Fee Paid Project stage: Request ML20199E2241986-06-18018 June 1986 Proposed Tech Specs,Deleting Surveillance Requirements for Reactor Bldg Upper Dome Air Circulators Project stage: Other ML20199E2091986-06-18018 June 1986 Application for Amend 121 to License DPR-54,changing Tech Spec 4.5.1.B to Delete Surveillance Requirements for Reactor Bldg Upper Dome Air Circulators.Safety Analysis & No Significant Hazards Evaluation Encl.Fee Paid Project stage: Request ML20214J3601986-08-0606 August 1986 Forwards Request for Addl Info Re Proposed Tech Spec Amend 148 Submitted by Util on 860613.Request Concerns Auxiliary Feedwater Pump Testing During Power Operation Project stage: RAI ML20214R7291986-09-19019 September 1986 Forwards Addl Info in Response to 860806 Request Re Proposed Amend 148 to License DPR-54,permitting Testing of Auxiliary Feedwater Pump During Conditions of Operation or Shutdown Project stage: Other ML20207N2261987-01-0707 January 1987 Responds to NRC Inquiries Re Amend 121 to License DPR-54. Advises That Upon NRC Approval of Amend,Emergency Procedures Will Be Revised Re Operability of Emergency Coolers or Containment Spray Sys for Min 30-day post-LOCA Period Project stage: Other ML20236J2461987-11-0303 November 1987 Forwards Amend 89 to License DPR-54 & Safety Evaluation. Amend Deletes Surveillance Requirements Associated W/Upper Dome Air Circulators in Tech Spec 4.5.2, Reactor Bldg Cooling Sys Project stage: Approval 1986-08-06 |
| ML20199E224 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/18/1986 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20199E214 | List: |
| References | |
| TAC-61869, TAC-61871, NUDOCS 8606230229 | |
| Download: ML20199E224 (1) | |
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Text
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.l. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.5.2 REACTOR BUILDING COOLING SYSTEMS Applicability Applies to testing of the Reactor Building cooling systems.
Objective To verify that the Reactor Building cooling systems are operable.
Specification 4.5.2.1 System Tests A. Reactor Building Spray System
.1 During each refueling interval a system test shall be conducted to demonstrate proper operation of the system.
A manual trip signal will be applied to demonstrate actuation of the Reactor Building spray system (except for Reactor Building motor-operated inlet valves which prevent water entering nozzles). Water will be circulated from the borated water storage tank through the Reactor Building spray pumps and returned through the test line to the borated water storage tank.
.2 Air will be introduced into the spray headers to verify the availability of the headers and spray nozzle at least every 10 years.
.3 The test will be considered satisfactory if visual observation and control board indication verifies that all components have responded to the actuation signal and the appropriate pump breakers shall have opened and closed, and all valves shall have completed their travel except the blocked Reactor Building inlet valve.
B. Reactor Building Euergency Cooling System
.1 During each refueling interval, a system test shall be conducted to demonstrate proper operation of the system.
121H The test shall be performed in accordance with the procedure summarized below:
- a. A manual trip signal will be applied to actuate the Reactor Building emergency cooling system for Reactor Building cooling operation.
Proposed Amendment 121 4-29 8606230229 860618 PDR ADOCK 05000312 P PDR
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