Proposed Tech Specs Incorporating Requirements for Reactor Vessel Level Indication Sys| ML17261A624 |
| Person / Time |
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| Site: |
Ginna  |
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| Issue date: |
09/24/1987 |
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| From: |
ROCHESTER GAS & ELECTRIC CORP. |
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| To: |
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| Shared Package |
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| ML17261A621 |
List: |
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| References |
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| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-2.E.1.2, TASK-2.F.1, TASK-2.F.2, TASK-2.G.1, TASK-TM NUDOCS 8710010029 |
| Download: ML17261A624 (10) |
|
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Text
Attachment A Revise the Technical Specification pages as follows:
Remove Insert page 3.5-15 page 3.5-15 page 4.1-7 page 4.1-7 "9710010029 87092+
PDR ~DGC~ 06000~44 PDR gj, p
'k TABLE 3.5-4 Accident Monitorin Instrumentation TOTAI REQUIRED MINIMUM NO. OF CHANNELS CHANNELS (7) OPERABLE (7)
- 1. Pressurizer Water Level (1)
- 2. Auxiliary Feedwater Flow Rate (2)(3) 2/steam generator 1/steam generator
- 3. Steam Generator Water Level - Wide 1/steam generator 1/steam generator Range (3)
- 4. Reactor Coolant System Subcooling Margin Monitor (4)
- 5. Pressurizer PORV Position indicator (5) 2/Valve 1/Valve
- 6. PORV Block Valve Position Indicator (1) 1/Valve 0/Valve
- 7. Pressurizer Safety Valve Position 2/Valve 1/Valve Indicator (5)
- 8. Containment Pressure (8)
- 9. Containment Water Level (Narrow Range, Sump A) 1(6) 1(6)
- 10. Containment Water Ievel (Wide Range, Sump B) ll. Core-Exit Thermocouples 4/core quadrant 2/core quadrant
- 12. Reactor Vessel Level Indication System Notes (1) Emergency power for pressurizer equipment, NUREG-0737, item II.G.l.
(2) Auxiliary feedwater system flow indication, NUREG-0737, item II.E.1.2.
'3) Only 2 out of the 3 indications (two steam generator auxiliary feedwater flow and one wide-range steam generator level) are required to be operable, NUREG-0737, item II.E.1.2.
(4) Instrumentation for detection of inadequate core cooling, NUREG-0737, item II.'F.2.1.
(5) Direct indication of relief and safety valve position, NUREG-0737, item II.D.3. Two channels include a primary detector and RTD as the backup detector.
(6) Operation may continue with less than the minimum channels operable provided that the requirements of Technical Specification 3.1.5.1 are met.
(7) See Specification 3.5.2 for required action.
(8) Containment pressure monitor, NUREG-0737, item II.F.1.4.
3s5 )5 Proposed
II TABLE 4. 1-1'CONTINUED)
Channel Descri tion Check Calibrate Test Remarks
- 25. Containment Pressure M Narrow range containment pressure
(-3.0, +3 psig) excluded
- 26. Steam Generator Pressure S
- 27. Turbine First Stage Pressure S
- 28. Emergency Plan Radiation Instruments
- 29. Environmental Monitors NA NA j 30. Loss of Voltage/Degraded NA I
Voltage 480 Volt Safeguards Bus
- 31. Trip of Main Feedwater Pumps NA NA
- 32. Steam Flow AVG R
- 34. Chlorine Detector, Control NA Room Air Intake
- 35. Ammonia Detector, Control NA 0
Room Air Intake
- 36. Radiation Detectors, Control NA Room Air Intake
- 37. Reactor Vessel Level NA Indication System
Attachment B The Reactor Vessel Z,evel Indication (RVZ,IS) was installed during the Spring 1986 refueling outage. A description of the RVLIS and plans for implementing revised Emergency Operating Procedures have previously been provided to the NRC in letters dated December 22, 1986, March 18, 1987 and September 18, 1987.
The RVLIS is being incorporated into the Ginna Technical Specifications to satisfy a NUREG-0737 requirement transmitted by a D.G. Eisenhut letter dated November 1, 1983. This letter provided "Model Technical Specifications" to be incorporated for the RVLIS. The proposed RVZ IS technical specifications are identical 'to the model specifications except they have been modified to listed fit the Ginna format. The detailed changes are on Table 1.
In accordance with 10CFR 50.91, this change to the Technical Specifications has been evaluated against, three criteria to determine if the operation of the facility in accordance with the proposed amendement would:
- l. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. Create the possibility of a new or different kind of accident previously evaluated; or
- 3. Involve a significant reduction in margin of safety.
The proposed changes do not,involve a significant'hange -in the probability of an accident previously evaluated because RVLIS is an instrument system involving small connections (3/8 inch) to the reactor coolant system. The RVLIS provides no automatic actuation on control functions and therefore will not. impact the probability of previously analyzed accidents. Incorporation of the RVLIS into Technical Specifications may decrease the consequences of certain accidents by implementing instrumentation designed to detect 'an'd aid in the response to inadequate core cooling.
The proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated because the changes involve only specifying operability and surveillance requirements of the RVLIS.
The proposed changes do not involve a significant reduction in margin of safety because specifying operability and surveill-ance requirements, in fact, increase safety margins by providing additional information useful to plant operators in responding to transient events and accidents.
1 e ~
II
Therefore, Rochester Gas and Electric submits that the issues associated with this amendment. request are outside the criteria of 10CFR50.91 and a no significant hazards finding is warranted.
~ ~
Table 1 Detailed Technical Specification Changes Location Descri tion of Chan e Reason for Chan e pp 3.5-15 added item 12 NUREG-0737 requirement pp 4.1-7 added item 37 NUREG-0737 requirement