ML17261A624
| ML17261A624 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/24/1987 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17261A621 | List: |
| References | |
| 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) | |
Text
Attachment A
Revise the Technical Specification pages as follows:
Remove Insert page 3.5-15 page 4.1-7 page 3.5-15 page 4.1-7 "9710010029 06000~44 87092+
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TABLE 3.5-4 Accident Monitorin Instrumentation TOTAI REQUIRED NO.
OF CHANNELS (7)
MINIMUM CHANNELS OPERABLE (7) 1.
Pressurizer Water Level (1) 2.
Auxiliary Feedwater Flow Rate (2)(3) 3.
Steam Generator Water Level - Wide Range (3) 2/steam generator 1/steam generator 1/steam generator 1/steam generator 4.
Reactor Coolant System Subcooling Margin Monitor (4) 5.
Pressurizer PORV Position indicator (5) 6.
PORV Block Valve Position Indicator (1) 7.
Pressurizer Safety Valve Position Indicator (5) 2/Valve 1/Valve 2/Valve 1/Valve 0/Valve 1/Valve 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 12.
Reactor Vessel Level Indication System 4/core quadrant 2/core quadrant Notes (1)
Emergency power for pressurizer equipment, NUREG-0737, item II.G.l.
(2)
'3)
Auxiliary feedwater system flow indication, NUREG-0737, item II.E.1.2.
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
Channel Descri tion TABLE 4. 1-1'CONTINUED)
Check Calibrate Test Remarks 25.
Containment Pressure 26.
Steam Generator Pressure S
27.
Turbine First Stage Pressure S
M Narrow range containment pressure
(-3.0,
+3 psig) excluded 28.
Emergency Plan Radiation Instruments 29.
j 30.
I Environmental Monitors Loss of Voltage/Degraded Voltage 480 Volt Safeguards Bus NA NA NA 31.
Trip of Main Feedwater Pumps NA 32.
Steam Flow AVG NA R
34.
Chlorine Detector, Control NA Room Air Intake 35.
0 36.
Ammonia Detector, Control Room Air Intake NA Radiation Detectors, Control NA Room Air Intake 37.
Reactor Vessel Level Indication System NA
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 fit the Ginna format.
The detailed changes are listed 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.
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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.
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Table 1
Detailed Technical Specification Changes Location pp 3.5-15 pp 4.1-7 Descri tion of Chan e
added item 12 added item 37 Reason for Chan e
NUREG-0737 requirement NUREG-0737 requirement