ML20151Y761
| ML20151Y761 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/06/1986 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20151Y754 | List: |
| References | |
| NUDOCS 8602130128 | |
| Download: ML20151Y761 (12) | |
Text
_.
L A*ITACllMENT 1 1
PROPOSED TECilNICAL SPECIFICATION Cl!ANGES l
UNIT 1 8602130120 060206 PDR ADOCK 05000330 P
TABLE 3.6-1 g
CONTAINMENT ISOLATION VALVES N:
VALVE ISOLATION TIME NUMBER FUNCTION (SEC.)
A.
PHASE "A" ISOLATION c
5 1.
MOV-1380 Reactor Coolant Pump Seal Water Return 10 a
2.
MOV-1381 Reactor Coolant Pump Seal Water Return 10 3.
Deleted 4
Deleted 5.
TV-1204A Reactor Coolant Letdown Line 10 6.
TV-1204B Reactor Coolant Letdown Line 10 7.
TV-S1100 Nitrogen to Pressurizer Relief Tank 60 y
3:
and SI Accumulators 8.
TV-DG100A Primary Drains Transfer Tank Pump Discharge 60 9.
TV-DB100B Primary Drains Transfer Tank Pump Discharge 60 10.
TV-DA100A Containment Sump Pump Discharge to Waste 60 Drain Tanks 11.
TV-DA100B Containment Sump Pump Discharge to Waste 60 Drain Tanks 12.
TV-BD100A Steam Generator Blowdown 60 13.
TV-BD100B Steam Generator Blowdown 60 14.
TV-BD100C Steam Generator Blowdown 60 15.
TV-BD100D Steam Generator Blowdown 60 16.
TV-BD100E Steam Generator Blowdown 60 17.
TV-BD100F Steam Generator Blowdown
TABLE 3.6-1 (Cont.)
5 VALVE ISOLATION TIME NUMBER FUNCTION (SEC.)
}
- 19. MOV-1836*
High Head Safety Injection to RCS Except Boron NA s
Injection Line i
c
- 20. MOV-1869B*
High Head Safety Injection to RCS Except Boron NA 5
Injection Line H
~
- 21. Deleted
- 22. Deleted
- 23. Deleted
- 24. MOV-1890*
LHSI Pump Discharge to Reactor Coolant System NA Hot Legs
- 25. MOV-1890B*
LHSI Pump Discharge to Reactor Coolant System NA Hot Legs i
- 26. MOV-1890C*
LHSI Pump Discharge to Reactor Coolant System NA Z
Cold Legs
- 27. MOV-1890D*
LHSI Pump Discharge to Reactor Coolant System NA Cold Legs
- 28. FCV-1160*
Loop Fill Header NA
- 29. MOV-1289A*
Charging Line NA
- 30. MOV-1867C*
High Head Safety Injection, Boron Injection Tank NA
- 31. MOV-1867D*
High Head Safety Injection, Boron Injection Tank NA
- 32. MOV-RS-100A*
Casing Cooling to Outside Recirculation Spray Pump NA
- 33. MOV-RS-100B*
Casing Cooling to Outside Recirculation Spray Pump NA
- 34. MOV-RS-101A*
Casing Cooling to Outside Recirculation Spray Pump NA
TABLE 3.6-1 (Con't.)
z VALVE ISOLATION TIME gj NUMBER FUNCTION (SEC) h G.
STEAM LINE ISOLATION I
1.
TV-MS-101Af Main Steam Line Trip Valve 5
Eq 2.
TV-MS-101Bf Main Steam Line Trip Valve 5
~
3.
TV-MS-101C#
Main Steam Line Trip Valve 5
H.
RELIEF None t
s~
iu
\\
)
- Valve not subject to Type "C" leakage test
- Valve position maintained by administrative control NA - Not applicable
- - Requires testing per Technical Specifications 4.6.3.1.la. or 4.6.3.1.2d.
TilIS PAGE INTENTIONALLY LEFT BLANK NORTH ANNA - UNIT 1 3/4 6-32
a u
a a
h 9
e A*lTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES UNIT 2 I
L l
l L
8 xd TABLE 3.6-1 CONTAINMENT ISOLATION VALVES gj I
VALVE ISOLATION TIME gj NUMBER FUNCTION (SEC.)
G A.
PFASE "A" ISOLATION g
1.
MOV-2380 Reactor Coolant Pump Seal Water Return 10 2.
MOV-2381 Reactor Coolant Pump Seal Water Return 10 3.
Deleted 4.
Deleted 5.
TV-2204A Reactor Coolant Letdown Line 10 6.
TV-2204B Reactor Coolant Letdown Line 10 p
7.
TV-S1200 Nitrogen to Pressurizer Relief Tank 60 and SI Accumulators
--o 8.
TV-DC200A Prinary Drains Transfer Tank Pump Discharge 60 9.
TV-DB200B Primary Drainn Transfer Tank Pump Discharge 60 10.
TV-DA200A Contain=ent Sump Pump Discharge to Waste 60 Drain Tanks 11.
TV-DA200B Containment Sump Pump Discharge to Waste 60 Drain Tanks 12.
TV-BD200A Steam Generator Blowdown 60 13.
TV-BD200B Steam Generator Blowdown 60 14.
TV-BD200C Steam Generator Blowdown 60 l
TABLE 3.6-1 (Con't.)
VALVE ISOLATION TIME NUMBER FUNCTION (SEC) gj
- 14. MOV-SW204B*
Service Water from Recirculation Spray NA Coolers i
5
- 15. MOV-SW204C*
Service Water from Recirculation Spray NA y
Coolers
- 16. MOV-SW204D*
Service Water from Recirculation Spray NA Coolers
- 17. TV-CV200*
Containment Air Ejector Suction NA
- 18. MOV-2869A*
High Head Safety Injection to RCS Except NA Boron Injection Line
- 19. MOV-2836*
High Head Safety Injection to RCS Except NA Boron Injection Line
- 20. MOV-2869B*
High Head Safety Injection to RCS Except NA
];
Boron Injection Line 5'
- 21. Deleted 5
- 22. Deleted
- 23. Deleted
- 24. MOV-2890A*
LHSI Pump Discharge to Reuctor Coolant System NA Hot Legs
- 25. MOV-2890B*
LHSI Pump Discharge to Reactor Coolant System NA Hot Legs
- 26. MOV-2890C*
LESI Pump Discharge to Reactor Coolant System NA Cold Legs
TABLE 3.6-1 (Con't.)
$=
VALVE ISOLATION TIME NUMBER FUNCTION (SEC)
E>
G.
STEAM LINE. ISOLATION s
~'
1.
TV-MS201A#
Main Steam Line Trip Valve 5
n 2.
TV-MS201Bf Main Steam Line Trip Valve 5
3.
TV-MS201C#
Main Steam Line Trip Valve 5
H.
RELIEF None M
c-i M
- Valve not subject to Type "C" leakage test
- Valve position maintained by administrative control NA - Not applicable
- - Requires testing per Technical Specifications 4.6.3.1.la. or 4.6.3.1.2d.
4 2
4 8
6 ATTACllMENT 3 4
DISCUSSION OF PROPOSED CHANGES 4
d 4
+
-,-.-nn
~
DISCUSSION OF FROPOSED CHANGE The -proposed changes to North Anna Unit 1 and Unit 2 Technical Specifications reficcts the addition of a new containment isolation valve in the letdown line on each unit. The two new valves (TV 1204A and 2204A) will function as the inside containment isolation valve and are designed to meet the operating criteria of the three existing parallel valves (HCV
- 1200A, B,
C and HCV 2200 A, B, C).
The new valves will replace the existing parallel isolation valves on table 3.6-1, containment isolation valves, of the Technical Specifications for both units.
In addition, l
relief valves RV-1203 and RV-2203 and remote manual valves HCV-1142 and HCV-2142 are being deleted from table 3.6-1 due to the addition of the new.
isolation valves.
The three parallel valves have demonstrated I
considerable maintenance problems in the past' and as a result prompted the l'
installation of the new isolation valves. The new valves are designed to -
minimize the leakage problems and will be of benefit from the aspects of ALARA concerns, lower maintenance requirements and less outage delays. It i
should be noted that the inside and outside containment isolation valves l
have been renumbered to meet Human Factors Guidelines. The existing parallel valves, the in-line relief valves and the remote manual valves will not be physically removed from the system. The parallel valves will continue to receive a close signal from the containment isolation actuation system. The new isolation valves are planned for installation during the next refueling outage for each unit.
10 CFR 50.59 Safety Review This change to move the existing containment isolation boundary, and modify North Anna Unit 1 and 2 Technical Specifications Table 3.6-1, by replacing the three existing letdown isolation valves, relief valve and remote manual valve with a single, new containment isolation r41ve does not constitute an "Unreviewed Safety Question" as defined in 10 CFR 50.59 for the following reasons:
1.
The change does not !ncrease the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report.
The new valves are designed consistent with the original Design Basis Criteria for Containment Isolation Valves and tha requirements of Reg.
Guide 1.97.
The modification does not functionally change the operation of the Letdown System beyond requiring the opening and closing of TV-1204A (TV-2204A) at the same time as TV-1204B (TV-22043). TV-1204A and TV-2204A will assume the Inside Containment Isolation function of HCV-1200A,B,C, RV-1203 and HCV-1142 and HCV-2200A,B,C, RV-2203 and HCV-2142.
This modification does not affect any existing accident analysis.
2.
The change does not create a possibility for an accident or malfunc-tion of a different type than any previously evaluated in the Final Safety Analysis Report.
The modification does not functionally change the operation of the Letdown System or change the containment
. =
isolation function. This modification does not affect any existing accident analyses.
3.
The change does not reduce the margin of safety as defined in the basis of any Technical Specification. The safety limits as defined in the Technical Specifications are not changed.
10 CFR 50.92 Significant Hazards Review The proposed changes do not pose a significant hazards consideration as defined in 10 CFR 50.92.
This conclusion is based upon the foregoing safety evaluation. We have also reviewed the types of license amendments that the NTC considers unlikely-to involve significant hazards considerations (Federal Register, Vol. 48, No. 67, April 6, 1983, p.
14870, " Standards for Determining Whether License Amendments Involve No Significant Hazards Considerations, Interim Final Report." ) and found none of the examples to be directly comparable. As stated previously, the proposed changes reflect the addition of a new containment isolation valve in the letdown line on each unit.
The new valve on each unit is functionally equivalent to and designed consistent with the original design criteria for the containment isolation valves which are being replaced.
2
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