ML20206G528
| ML20206G528 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/27/1987 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206G531 | List: |
| References | |
| NUDOCS 8704150031 | |
| Download: ML20206G528 (29) | |
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- o UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
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t VIRf; INIA ELECTRIC AND POWER COMPANY _
I OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338
.I NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 9 License No. NPF-4 l
1.
The Nuclear Regulatory Comission (the Commissioni has found that:
t A.
The application for amendment by Virginia Electric and Power Company,
)
et al., (the licensee) dated September 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of l
the Comission;
)
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; r
D.
The issuance of this amendment will not be inimical to the comon i
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements 3
-l have been satisfied.
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o Accordingly, the license is amended by chances to the Technical Speci-j 2.
fications as indicated in the attachment to this license amendment, and paragraph 2.0.f ?) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
i f
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised throuch Amendment No. 91, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective within sixty days of the date of
?
3 3.
issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
Lester S. Rubenstein, Director PWR Pro.iect Directorate #?.
Division of PWR Licensinq-A j
Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 27, 1987 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 93 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338
)
]
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by l!
amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document 1
completeness.
l Page 3-3/4 3-53a i
i 3/4 7-72 3/4 7-74 c
A i
3/4 8-4a 3/4 8-4b j
B3/4 7-8
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5 TABLE 3.3-11 f
FIRE DETECTION INSTRUMENTATION MINIMUM DETECTORS BEQUIRED HEAT l SMOKE INSTRUMENT LOCATION t,,
1.
Reactor Containment a.
Reactor Coolant Pumps 1/ pump
- j b.
Residual Heat Removal Pump Area 3
i c.
Cable Penetration Area 7
8 2
d.
Recirculation Air System
?
?
2.
Control Room a.
Under Floor - Loop 1 2
2
{
b.
Under Floor - Loop 2 2
1 3
)
c.
Normal Air Supply #
1 d.
Emergency Air Supply 10 l
e.
Ceiling Area 1
f.
Return Air Duct t
3.
Cable Spreading Room 3
4 l
4.
Primary Cable Vault and Tunnel 2
3
~5.
Service Building Cable Vault and Tunnel 5
4 7
6.
Emergency Switchgear Rooms 1
a.
Emergency Air Supply l
b.
Emergency Switchgear and Air 7
Conditioning Rooms
)j 7.
Station Battery Room 1/ room I
8.
Diesel Generators 2/ room 9.
Fuel Oil Pump House #
a.
Room 1 1
1 i
b.
Room 2 1
1 c.
Motor Control Center Room 1
- 10. Rod Control Equipment and Motor Control Center Room (Elevation 280.0) 2
- 11. Auxiliary Building a.
Charging Pump Cubicles 1/ cubicle b.
Exhaust Duct Northeast-Cubicles)#
1 c.
Exhaust' Duct SouthCentral-Cubicles)#
1 I'
d.
Exhaust Duct Northwest-Cubicles)#
1 I
NORTH ANNA - UNIT 1 3/4 3-53 Amendment No. 3. 51
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TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION MINIMUM DETECTORS REQUIRED
]
HEAT _
SM0KE i
INSTRUMENT LOCATION 4
5 Auxiliary Building (cont'd) e.
General Area Elevation 244'#
1 4
f.
General Area Elevatic, 259'#
g.
General Area Elevation 274'#
14 y>
General Area Elevation 291'#
4 h.
j
- i. Charcoal Filters q
3/ room 4
1.
Intake Side #
1 2.
Outlet Side #
3/ room a'
8
,i.
- 12. Service Water Pump Housef 1
1,
- 13. Auxiliary Service Water Pump House #
j
- 14. Auxiliary Feed Water Pump House 5
I a.
Turbine Pump Room 3
.i b.
Motor Pump Room 1
p
- 15. Quench Spray Pump House a.
Main Floor 2
1 b.
Basement 4
(
- 16. Safeguards Area Ventilation 1
a.
System Exhaust Duct
- 17. Main Steam Valve House 1
1
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- 18. Fuel Building #
10
- 19. Casing Cooling Pump House 1
f.
- 20. Post Accident Hydrogen Recombiner Vault #
1 1
1 y
- 21. Fire Pump House #
b
- 22. Control Room Air Conditioning Chiller Room 1
- 23. Service Water Valve House #
a.
West Room 2
l b.
Northeast Room 1
c.
Southeast Room 1
4
- ~ An RCP bearing or motor temperature may be substituted for an inoperable RCP heat j'
detector provided the bearing or motor temperature (s) is monitored at least once per hour when the RCP is in operation.
- Common to Units 1 and 2.
NORTH ANNA - UNIT 1 3/4 3-53a Amendment No. 57, 91 i
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TABLE 3.7-5_
CitNtES ALL0tM8tE TOTAL SETTLEENT OR DIFFERENTIAL SETTLEMENT FOR CLA i
ALLOWABLE RLOWA8tE DIFFERENTIAL i
z TOTAL SETTLEENT*
SETTLEENT*
l (FEET) _
_(FEET) r
-4 SETTLEE NT STRUCTURE /Copr0NENT_
l 2
_ POINT _
N/A SETTLEENT STRUCTINif 0.12
>2, Contatsment Unit 1 M/A POINT _
223 fuel Dutiding 0.12 130 Auxi11ary But1d1ng 129 0.04 Conta1mment Unit 1 N/A
}
Unit 1 Safeguards Area 130 142 k
0.04 Contalment Unit 1 N/A Unit 1 Safeguards Area 143 145 a
0.12 E
Cantalsment Unit 1 N/A Unit 1 Main Steam Valve House I
144 239 Contalsment Unit 1 N/A 0.12 243,199.132 Service Butiding j
149 N/A 0.07 Containment Unit 1 untt 1 Main Steam Valve House f
144 239 N/A 0,08 a
Safepards Unit 1 Untt 1 Main Steam Valve House i
146 Austilary Sutiding N/A 0.08
?
238 Untt 1 Main Steam Valve House 128 239 0.05 Asutilary Butiding M/A
'i 129
';d 223 Fuel Butiding 0.05 t
Aux 111ery antiding N/A 129 Fuel Buf1 ding 224 0.07 Auxlitary tutidtag N/A Service Butiding Tunnel 123 0.22 from 7/77 119 Austilary Sutiding North $1de of Expaaston Joint N/A 122 15.16 Service Water Piping at SWPH Service Unter Pump Neuse 17,18 0.04 7 or 10 N/A Unit 1 Main Steam Valve House 238 0.03 from 7/77 ServiceButiding(E-5.E-6)
N/A Unit 2 Main Steen Valve House 243.132
- s 113
- 5ervice Rutiding (E-14)
I 117 N/A 0.12 Aust11ery Feeesater Pusy 248 Pipe Tunnel 222 Mouse - Unit 1 2
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TABLE 3.7-5 l
ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES i
3 ALLOWABLE ALLOWABLE g
TOTAL DIFFERENTIAL 3
SETTLEMENT SETTLEMENT SETTLEMENT
- SETTLEMENT
- POINT STRUCTURE POINT STRUCTURE / COMPONENT (FEET)
(FEET) e 15.16,17,18 North Side of Expansion Joint 0.22 from 8/78 N/A Service Water Piping at SWPH C
E 228 Decontamination Building 250 Pipe Tunnel N/A 0.06 226 Fuel Building 251 Waste Gas Decay Tank N/A 0.06 3
Enclosure 5
~8 Service Water Rump House H-569,H-584 Pipe Hanger in Reservdir N/A 0.17 114 Service Building (E-17) 0.09 N/A 141 Safeguards Area - Unit 1 253 Unit 1-Casing Cooling Bldg.
N/A 0.12 from 2/79 158
- Turbine Building (B-9 1/2) 0.06 N/A 245,246 Fuel Oil Pump House 0.03 N/A p
206,207 Boron Recovery Tank Dike 0.03 N/A
{
208.209 204 Circulating Water Intake Structure 0.15 N/A 25.26 Service Water Valve House 0.32 (see N/A note) g 27.28 f
29,30 Service Wdter Tie-in Vault 0.12 (see N/A 31,32 ntrte)
NOTEt From date of Piping Tie-in z
Unless otherwise indicated, allowable settlements are from baseline established in May 1976 or reference
?
evaluations corrected to the May 1976 survey.
.F Critical differential settlement is downward of Point 117 with respect to Point 113.
3 b
- Not Class 1 structure, but settlements affects Class 1 pipeline.
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PLANT SYSTEMS 3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR h
LIMITING CONDITION FOR OPERATION 3.7.13 The goundwater level of the service water reservoir shall not exceed the elevation at the locations listed in Table 3.7-6.
The flow of ground-water from the drains beneath the pumphouse shall not exceed the values given in Table 3.7-6.
l APPLICABILITY: All MODES.
i ACTION:
i With the groundwater level of the service water reservoir or the groundwater flow rate exceeding any of the limits of Table 3.7-6, an engineering evalua-I e
tion shall be perfomed by a Licensed Civil Engineer to determine the cause of the high ground water or flow rates and the influence on the stability of d
the service water reservoir and pumphouse. A Special Report shall be 5
prepared and submitted to the Comission pursuant to Specification-6.9.2 within 90 days, containing the results of the evaluation and any corrective action detemined to be necessary.
I SURVEILLANCE REQUIREMENTS 4.7.13.1 The groundwater level within the dike of the service water l
reservoir as detemined by monitoring the piezometers shall be within limits I
l presented in Table 3.7-6.
Measurements shall be performed at least once per 6 months. The groundwater flow rate shall be detemined by measurements at the drain outlet gallery. Flow rate measurements shall be taken at the same frequency as the piezometers (that is once per every 6 months) and the flow A visual inspection i,
rate shall not exceed that established in Table 3.7-6.
of the clarity of the outflow from each drain shall be perfomed in conjunc-I
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tion with the flow monitoring effort.
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i NORTH ANNA - UNIT 1 3/4 7-73 Amendment No. J2,57
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ALLOWABLE GROUNDWATER LEVELS - SERVICE WATER RESERVOIR
[
PIEZ0 METER PIEZ0 METER ALLOWABLE GROUN0 WATER ELEVATION, f
3 NO.
LOCATION Mean Sea Level (feet) 277 a
)
10 SE, toe
~
11 SWPH, (Units 1 & 2) crest 280 12 SWPH, (Units 1 & 2) toe 285 13 SWPH, (Units 1 & 2) crest 280 14 SWPH, (Units 1 & 2) crest 280 ca3 280 15 SE, crest y
280 16 SE, crest 280 e
17 SE, crest U
18 SWH (Units 1 & 2) 295 l
ALLOWABLE DRAIN FLOW RATE
[
(gallons per minute) a DRAIN OUTLETS LOCATION P.g 1 through 6 Drainage Gallery FLOW RATE SHALL NOT EXCEED 8.5 GALLONS PER MINUTE (gpm)
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TABLE 4.8-1 3
LIST OF LOAD SEQUENCING TIMERS AND DESIGN SETPOINT "H"
BUS l
f INITIATING (I)
TOLERANCE TIMER SET POINT IDENTIFICATION _
(SECONDS)_
SIGNAL (SECONDS) g 1FWEA01-62 20 SI 11.00 I
1FWEA01-62A 25 LOP
+1.25 3s 1SWEA03-62 10 LOP
+0.50 s
1RSOA01-62B 35 LOP 11.75 i
a
j CDA 121.0 1RSOA01-62A 210 j
f 1CCPA01-62Y 15 LOP 10.75 1CCPA01-62X 20 LOP 11.00 a
1 1RSIA01-62A 20 LOP 11.00
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1RSIA01-62 195 CDA 19.75 1QSSA01-62A 15 LOP 10.75
),
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1HVRA03-62 30 LOP 11.50 1
I-1HVRA04-62 10 LOP 10.50 s
h k
1HVRB04-62 10 LOP 10.50 q
f l,l 1PGSA02-62A 10 (2) 10.50 f
1ENSH06-62A 15 LOP 10.75
'f 1HVRC04-62 10 LOP 10.50 l&
1SWSA35-62A1A 15 SI 11.50 1SWSA35-6281 A 15 SI 11.50 li L
Amendment No. 91 3/4 8-4a NORTH ANNA UNIT 1
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.i TABLE 4.8-1 (Continued) ij LIST OF LOAD SEQUENCING TIMERS AND DESIGN SETPOINTS t
"J" BUS h.
Aj II)
A TIMER SET POINT INITIATING TOLERANCE IDENTIFICATION (SECONDS)
SIGNAL (SECONDS) i 1FWEB01-62 20 SI 11.00 j
1FWEB01-62A 25 LOP 11.25
).
1SWEB03-62 10 LOP 10.50 1RSOB01-628 35 LOP 11.75 I.
l 1RSOB01-62A 210 CDA 121.0
]
1CCPB01-62Y 15 LOP 10.75 1CCPB01-62X 20 LOP 11.00 f
1RSIB01-62A 20 LOP 11.00 1RSIB01-62 195 CDA 19.75 h.
3 1QSSB01-62A 15 LOP 10.75 1
k 1HVRB03-62 30 LOP 11.50 h
1HVRD04-62 10 LOP 10.50 il 1HVRE04-62 10 LOP 10.50
}
lHVRF04-62 10 LOP
+0.50 h
IPGSB02-62A 10 (2) 10.50 2
1ENSJ06-62A 15 LOP 10.75 1SWSB35-62A1B 15 SI 11.50 1SWSB35-62B1B 15 SI 11.50 (1) SI - Safety injection LOP - Loss of Offsite Power CDA - Containment Depressurization Actuation (2) Low primary grade water header pressure NORTH ANNA UNIT I 3/4 8-4b Amendment No. 91 l
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3 PLANT SYSTEMS j
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BASES
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i Reference Monitorina Points Limitino Item I
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Containment Unit 1 Fuel Building Fuel Transfer Tube j
Containment Unit 1 Auxiliary Building 3"-WGCB-14 Containment Unit 1 Unit 1 Safeguards Area 12"-S1-1 4
Containment Unit 1 Unit 1 Main Steam Valve House 6"-SI-16 L
Containment Unit 1 Service Building (E-3) 32"-SH P-2 4,
Safeguards Area Unit 1 Unit 1 Main Steam Valve House 8"-QS-3 j
Auxiliary Building Unit 1 Main Steam Valve House 8"-WS-ll3 g
Auxiliary Building Fuel Building 4"-RP-28 4
Auxiliary Building Service Building Tunnel 24"-WS-102 Service Water Pump G
House Service Water Piping 0 SWPH Expansion Joint j
Service Water Pump 1
House Pipe Hanger in Reservoir 24" -WS-11-151-Q3
)
Service Water Pump House Service Water Pump House Mat i
Service Bldg. (E-5,E-6) Unit 1 Main Steam Valve House 24"-WS-26-151-Q3 i
Service Bldg. (E-14)
Unit 2 Main Steam Valve House 24"-US-426-151-Q3 3
Pump House - Unit 1 Pipe Tunnel 3"-WAPD-9-601-Q3 j
Decontamination Bldg.
Pipe Tunnel 3"-CC-90-151-Q3 1
Fuel Building Waste Gas Decay Tk. Enclosure 4"-GW-30-154-03 i
Safeguards Area Unit 1 Unit 1 Casing Cooling Building 6"-RS-E15-153A-Q3 l
The items limiting total settlement of structures are as follows:
I Monitoring Points Limitino Items i
Service Water Pip ng at SWPH 36"-WS-1-151-Q3 Service Building E-17) 36"-WS-1-151-Q3 Turbine Building B-91/2) 24"-WS-25-151-Q3 Fuel Oil Pump House 2 1/2"-F0F-151-S Boron Recovery Tank Dike NOTE (1)
Circulating Water Intake Service Water Piping expansion Structure joint Service Water Valve House 32 1/4" - WS-084-151-03 Service Water Tie-in Vault 36" - WS-1-151-Q3 Note (1) No settlement expected; settlement in excess of 0.03 ft. would indicate an abnormality.
(2) Measurements of certain points are required to be performed at least once per 31 days for the first five years of facility operation to provide additional settlement information.
NORTH ANNA - UNIT 1 B 3/4 7-8 Amendment No. II, 91 1
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UNITED STATES og NUCLEAR REGULATORY COMMISSION i
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WASHINGTON. D. C 20555 j
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i VIRGINIA ELECTRIC AND POWER COMPANY f)
OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANSA POWED STATION, UNIT NO. ?
AMEN 0 MENT TO FACILITY OPFRATING LICENSF Amendment No. 76 License No. NPF-7 P
r 1.
The Nuclear Regulatory Commission (the Commission) has found that:
F A.
The application for amendment by Virginia Electric and Power Company, et al., (the licenseei dated September 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance lii that the activities authorized by this amendment can be conducted without endancering the health and safety of the public, and fiil that such activities will be conducted in compliance with the Commission's regulations; l
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; j
l and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable reautrements t'
have been satisfied.
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2-2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby l
amended to read as follows:
(2) Technical Specificatior.s l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
This license amendment is effective within sixty days'of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION I
e m.
S-dom tester S. Rubenstein. Director t
PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 27, 1987 l
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!l ATTACHMENT TO LICENSE AMENOFENT NO. 76 i
1 TO FACILITY OPERATING LICENSE NO. NPF-7 I
DOCKET NO. 50-339 s
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Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by i
amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document 1
completeness.
j' Page l-3/4 3-50a 2
3/4 7-55 I.
3/4 7-58 d
3/4 8-7 j
3/4 8-8 3/4 8-?2 3/4 8-23 3/4 8-24 3/4 8-25 hl 83/4 7-8 1
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5 TABLE 3.3-11
(
FIRE DETECTION INSTRUMENTATION _
e MINIMUM DETECTORS REQUIRED a
SM0KE t
HEAT _
i INSTRUMENT LOCATION _
q Auxiliary Building (cont'd) 1
~4 General Area Elevation 244'#
14 e.
General Area Elevation 259'#
f.
4 General Area Elevation 274'#
?
g.
General Area Elevation 291'#
l h.i. Charcoal Filters 3/ room 1.
Intake Side #
3/ room 2.
Outlet Side #
l 8
- 12. Service Water Pump House #
- 13. Auxiliary Service Water Pump Housef i.
- 14. Auxiliary Feed Water Pump House 1
3 Turbine Pump Room a.
b.
Motor Pump Room j
t
- 15. Quench Spray Pump House
~
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.2 lI Main Floor 4
?
a.
b.
Basement
- 16. Safeguards-Area Ventilation 1
System Exhaust Duct a.
1
- 17. Main Steam Valve House l
10
- 18. Fuel Buildingf 1
i i
- 19. Casing Cooling Pump House 1
5
- 20. Post Accident Hydrogen Recombiner Vault #
- 21. Fire Pump House #
1
- 22. Control Room Air Conditioning Chiller Room
- 23. Service Water Valve Housef 2
a.
West Room 1
b.
Northeast Room 1
c.
Southeast Room heat
l
- Common to Units 1 and 2.
Amendment ilo. 35,76 l
3/4 3-50a l
NORTH ANNA - UNIT 2
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TABLE 3.7-5 (Continued) f
- =I ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEME h
ALLOWABLE ALLOWABLE i"
TOTAL DIFFERENTIAL E
SETTLEMENT
- SETTLEMENT
- STRUCTURE / COMPONENT (FEET)
(FEET)-
4 SETTLEMENT SETTLEMENT POINT- _
ro STRUCTURE N/A 0.06 POINT Waste Gas Decay Tank Enclosure 251 226 Fuel Building Unit 2 Casing Cooling Building N/A 0.12 254 Safeguards Area Unit 2 from 2/79 104 i
N/A 0.22 Service Water Piping at SWPH 15, 16, from'7/77 7, 10 Service Water Pump North Side of Expansion Joint 17, or 18 House N/A 0.17 y
H-569 Pipe Hanger in Reservoir Service Water Pump House E
8 H-584 O.22 from 8/78 N/A
~
Service Water Piping at SWPH 15,16, 3
17,'18 North Side of Expansion Joint 0.15 N/A Circulating Water Intake 204 Structure 0.06 N/A
- Turbine Building R.
158 (B-9 1/2) 0.09 N/A
=
~
Service Building (E-17) 0.03 N/A R
114
,F 245, 246 Fuel Oil Pump House 0.03 N/A Boron '& wery Tank Dike 206 207, I
O.32 (see note) N/A a*
208, 209 Service Water Valve House 0.12 (see note) N/A 25,26,27,28 Service Water Tie-in Vault
}
c, 29,30,31,32 From date of piping tie-in NOTE:
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i TABLE 3.7-5 (Continued) f 5
ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 4
x 4
>g s
e c-h.
e-e a
N Unless otherwise indicated, allowable settlements are from base-line elevations established in M or reference elevations corrected to the May 1976 survey.
[A Critical differential settlement is downward movement of Point 117 with respect to Point 113.
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- Not Class 1 structure, but se t ement affects Class 1 pipeline.
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PLANT SYSTEMS i_
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GROUNDWATER LEVEL-5ER/ ICE WATER RESERVOIR
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3/4.7.13 q
p-IMITING CONDITION FOR OPERATION L
3.7.13 The groundwater level of the service water reservoir (comon to Units 1 and 2) shall not exceed the elevation at the locat Table 3.7-6.
jl shall not exceed the values given in Table 3.7-6.
APPLICABILITY: All MODES.
s i
ACTION:
With the groundwater level of the service water reservoir or the ground l
water flow rate exceeding any of the limits of Table 3 l
cause of the high ground water or flow rates and the influence on theA Spec stability of the service water reservoir and pumphouse.
shall be prepared and submitted to the Commission pursuant to Specifica-tion 6.9.2 within 90 days, containing the results of the evaluation and i
I any corrective action determined to be necessary.
l SURVEILLANCE REQUIREMENTS ll The groundwater level within the dike of the service water reservoir as determined by monitoring the piezometers shall be wit 4.7.13.1 i.
limits presented in Table 3.7-6.The groundwater flow rate shall be determined i
once per 6 months.
Flow rate measurements shal measurements at the drain outlet gallery.
taken at the same frequency as the piezometers (that is once per every 6
[
months) and the flow rate shall not exceed that established d.
A visual inspection of the clarity of the outflow from each drain shall be Ii performed in conjunction with the flow monitoring effort.
j 1 e-!
i 1
!=
i l
l i
~
i 1;0RTH ANNA - UNIT 2 3/4 7-57 Amendment No. 39
- n.-. - - - ~ _ _ -.-
..-...-c.,.,
.. m _ -.
I
?
I TABLE 3.7-6 g
a z
E ALLOWABLE GROUNDWATER LEVELS - SERVICE WATER RESERVOIR I
t
[
PIEZ0 METER PIEZ0 HETER ALLOWABLE GROUNDWATER ELEVATION 2
H NO.
LOCATION Mean Sea Level (feet) ro 10 SE, toe 277 11 SWPH, (Units 1 & 2) crest 280 l
12 SWPH, (Units 1 & 2) toe 285 13 SWPH, (Units 1 & 2) crest 280 14 SWPH, (Units 1 & 2) crest 280
[
15 SE, crest 280 g
p 16 SE, crest 280 E
17 SE, crest 280 18 SWVH (Units 1 & 2) 295 l
ALLOWABLE DRAIN FLOWRATE DRAIN OUTLETS LOCATION (gallons per minute)
E 1 through 6 Drainage Gallery FLOW RATE SHALL NOT EXCEED
=
{
8.5 GALLONS PER MINUTE (9pm) a s
F 7
L
- u..... _.,-.m
- m. 2
....r.w.eu...
e _..m 3
I i
(
TABLE 4.8-1 LIST OF LOAD SEQUENCING TIMERS AND DESIGN SETPOINTS "H"
BUS s
b INITIATING (I)
TOLERANCE SET POINT IDENTIFICATION (SECONDS)
SIGNAL (SECONDS)
TIMER 20 SI 11.00 2FWEA01-62 j
25 LOP 11.25 3
2FWEA01-62A l
10 LOP 20.50 25WEA03-62 35 LOP 11.75 4
2RSOA01-62B 2RSOA01-62A 210 COA 121.0 i \\
15 LOP 10.75 1
2CCPA01-62Y 9
2CCPA01-62X 20 LOP 11.00 5
2RSIA01-62A 20 LOP
- 1.00 e
195 CDA 19.75 l
2RSIA01-62 15 LOP 10.75 2QSSA01-62A~~
2HVRA03-62 30 LOP 11.50 10 LOP 10.50 2HVRA04-62 10 LOP 10.50 q
i 2HVRB04-62 i
2HVRC04-62 10 LOP 10.50 f
~
i 15 LOP 20.75 2ENSH06-62A i,,
25WSA35-62A2A 15 SI 11.50 2SWSA35-62B2A 15 SI 11.50 I
I Amendment No. 76 i
NORTH ANNA - UNIT 2 3/4 8-7 h
. ~.. -....
..n.
..., a. w,
. :~m ~.n n a c.;.=....-
. a. c a..,.:
. x.w...w z =x'.n n o
TABLE 4.8-1 (Continued)
LIST OF LOAD SEQUENCING TIMERS AND DESIGN SETPOINTS "J"
BUS h
TIMER SET POINT INITIATING (I)
TOLERANCE 1
IDENTIFICATION (SECONOS)
SIGNAL (SECONDS) 1 2FWEB01-62 20 SI 11.00 2FWEB01-62A 25 LOP 11.25 25 WEB 03-62 10 LOP 10.50 2R50B01-62B 35 LOP 11.75 d' i j
2RSOB01-62A 210 CDA 121.0 4
2CCPB01-62Y 15 LOP 10.75 f
2CCPB01-62X 20 LOP 11.00 ii 2RSIB01-62A 20 LOP 11.00 2RSIB01 62 195 CDA 19.75 2QSSB01-62A 15 LOP 10.75 2HVRB03-62 30 LOP 11.50 5
2HVRD04-62 10 LOP 10.50 2HVRE04-62 10 LOP 10.50
.4 2HVRF04-62 10 LOP 10.50
)
2ENSJ06-62A 15 LOP 10.75 2SUSB35-62A2B 15 SI
+1.50
)
25WSB35-62B2C 15 SI
+1. 50 i
(1) SI - Safety Injection LOP - Loss of Offsite Power CDA - Containment Depressurization Actuation
}
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NORTH ANNA - UNIT 2 3/4 8-8 Amendment No. 76 l
n.
-. - c.. ~
-._as..: :,, -. u. -..,
.x.
.=c..
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1 h
1, ELECTRICAL p0WER SYSTEMS YPASS DEVICES MOTOR-0PERATED VALVES THERMAL OVERLOAD PROT i
)
LIMITING CONDITION FOR OPERATION i.
2 1
1 i
l The thermal overload protection and/or bypass devices, int i
2 shall be OPERABLE.
i the motor starter, of each valve listed in Table 3.8.
3.8.2.6 i
Whenever the motor-operated valve is required to be j
d APPLICABILITY _:
j OPERA 8LE.
?
ACTION:
/
bypass devices With one or more of the thermal overload protectio priate 1
j ACTION Statement (s) for the affected valve (s),
s*
i
- 5 l,
SURVEILLANCE REQUIREMENTS I
The above required thermal overlor.d protection and/or by 4.S.2.6 if shall be demonstrated OPERABLE; IONAL At least once per 18 mon *,ns, by the performance of a CH f
TEST of the bypass ciresitry for those thermal overload device
- F a.
{ y.
j ]
which are either:
Continuously bypassed and temporarily p g
ig 1.
!n; i
or j i; Normally in force during plant operation and bypassed unde i
2.
l accident conditions.
At least once per 18 months by the performance of a CHA ATION of a representative sample of at le b.
d
==
device is calibrated at least once per 6 years.
i I
NORTH ANNA - UNIT 2 3/4 8-21 f
.a ap u.
w...w
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. u m..a. = :,:1: a a, v m.u. - :. n.:.;.. a w,::..
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TABLE 3.8-2 MOTOR-OPERATED VALVES-THERMAL OVERLOAD PROTECTION AND/0R BYPASS DEVICES i
Function Bypass Device Valve Number No MOV-QS200A Quench Spray Pump Suction Valve No MOV-QS200B Quench Spray Pump Suction Valve No MOV-QS201A Quench Spray Pump Discharge Valve y
No Quench Spray Pump Discharge Valve MOV-QS201B No Chemical Addition to Refueling Water. Storage Tank MOV-QS202A Valve No Chemical Addition to Refueling Water Storage Tank MOV-QS202B Valve No
> el MOV-RS200A Casing Cooling to Outside Recirculation Spray Pump No MOV-RS200B Casing Cooling to Outside Recirculation Spray Pump No MOV-RS201A Casing Cooling to Outside Recirculation Spray Pump No MOV-RS201B Casing Cooling to Outside Recirculation Spray Pump No i
MOV-RS255A Outside Recirculation Spray Pump Suction Valve No j
MOV-RS255B Outside Recirculation Spray Pump Suction Valve No Outside Recirculation Spray Pump Discharge Valve MOV-RS256A No Outside Recirculation Spray Pump Discharge Valve MOV-RS256B No MOV-SW201A Recirculation Spray Heat Exchanger Supply Header Isolation No MOV-SW201B Recirculation Spray Heat Exchanger Supply Header Isolation No MOV-SW201C Recirculation Spray Heat Exchanger Supply Header l
Isolation No 5
MOV-SW201D Recirculation Spray Heat Exchanger Supply Header Isolation No MOV-SW203A Recirculation Spray Heat Exchanger Supply Shutoff No Recirculation Spray Heat Exchanger Supply Shutoff MOV-SW203B No Recirculation Spray Heat Exchanger Supply Shutoff MOV-SW203C No Recirculation Spray Heat Exchanger Supply Shutoff MOV-SW203D No Recirculation Spray Heat Exchanger Supply Header MOV-SW202A i
Crossover Isolation Valve No MOV-SW206A Recirculation Spray Heat Exchanger Supply Header Crossover Isolation Valve No MOV-SW202B Recirculation Spray Heat Exchanger Supply Header Isolation No l
Recirculation Spray Heat Exchanger Supply Header MOV-SW206B Isolation No MOV-SW204A Return from Recirculation Spray Heat Exchanger No MOV-SW204B Return from Recirculation Spray Heat Exchanger No MOV-SW204C Return from Recirculation Spray Heat Exchanger 4
No j
MOV-SW204D Return from Recirculation Spray Heat Exchanger No P
MOV-SW205A Recirculation Spray Heat Exchanger Return Header y
Isolation No Recirculation Spray Heat Exchanger Return Header i
MOV-SW205B C
Isolation j
d.
NORTH ANNA - UNIT 2 3/4 8-22 Amendment No. 76 9
n.-
mmm-.
-.~..~~.u.:
=. m... w
~.,.n n w -..
ji i
.I A
TABLE 3.8-2 (Continued]
4 CTION j
MOTOR-OPERATED VALVES-THERMAL OVE AND/OR BYPASS DEVICES
(
Bypass Device Function i
No i
Valve Number Recirculation Spray Heat Exchanger Return Header i
/
.No d
i MOV-SW205C Recirculation Spray Heat Exchanger Return Hea er
)
Isolation No 7
MOV-SW20SO Component Cooling Heat Exchanger Su f
Isolation No No MOV-SW208A No f
4 HOV-SW2088 Supply to Air Cooling Coils No l
MOV-SW210A Supply to Air Cooling CoilsReturn from Air Cooling No i
Valve No
,)
l 30V-SW214A Return from Air Cooling Coils Auxiliary S.W. Pump Discharge Header Isolat on Valve No g'
MOV-SW214B Auxiliary S.W. Pump Discharge Heade Valve No f
MOV-SW215A No MOV-SW215B No ij MOV-SW217 Fuel Pit Coolers Supply Header No l1 MOV-SW213A Fuel Pit Coolers Supply HeaderCir. Water Intake Y
MOV-SW2138 1
j MOV-SW219 Isolation Valve No No 1l S.W. Discharge to Circ. Tunnel MOV-SW220A S.W. Discharge to Circ. Tunnel 2 1 No f:
MOV-SW2208 SWR Spray Header No No f *l Ji MOV-SW221 A SWR Spray Header No j
MOV-SW221B SWR Spray Header No MOV-SW222A SWR Spray Header No MOV-SW222B SWR Spray Bypass No l
MOV-SW223A Aux. Steam Generator Feedpump Discharge Valve SWR Spray Bypass
,f,
MOV-SW223B No Aux. Steam Generator Feedpump Discharge Valve jbt MOV-FW200A No Aux. Steam Generator Feedpump Disch No MOV-FW2008 No
- - f MOV-FW200C No j
C MOV-FW2000 Emergency Control Room Vent No MOV-HV204-1 Emergency Control Room Vent
~
MOV-HV204-2 A/C Control Room Chiller Outlet No l
MOV-HV211A A/C Control Room Chiller Outlet
]
No MOV-HV211B A/C Control Room Chiller Outlet No 1
No MOV-HV211C A/C Cond. Water Discharge lW No MOV-HV213A A/C Cond. Water Discharge No MOV-HV213B A/C Cond. Water Discharge j
No MOV-HV213C Emergency Air Supply No MOV-HV218-1 Emergency Air Supply Residual Heat Removal Inlet Iso No MOV-HV218-2 No MOV-2700 Residual Heat Removal Outlet Isolation No MOV-2701 Residual Heat Removal Outlet Isolation No MOV-2720A Reactor Coolant System Loop A Hot Leg Stop Valve No f
MOV-2720B Reactor Coolant System Loop 8 Not Leg Stop Valve No MOV-2590 Reactor Coolant System Loop C Hot 4
No f
MOV-2592 MOV-2594 9
r MOV-2591 Amendment No. 76 1
3/4 8-23 l
NORTH ANNA - UNIT 2
)
b 1
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.- m.. m,
- =m m.m.m m=.., e
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TABLE 3.8-2 (Continued)
MOTOR-0PER/,TED VALVES-THERMAL OVERLOAD PROTECTION AND/OR BYPAS5 DEVICES Valve Number Function Bypass Device ll MOV-2593 Reactor Coolant System Loop B Cold Leg Stop Valve No MOV-2595 Reactor Coolant System Loop C Cold Leg Stop Valve No MOV-2585 Reactor Coolant System Loop A Bypass No
)
MOV-2586 Reactor Coolant System Loop B Bypass No MOV-2587 Reactor Coolant System Loop C Bypass No MOV-2381 RCP Seal Leakoff Isolation Valve No MOV-2380 RCP Seal Leakoff Isolation Valve
'No MOV-2535 Reactor Coolant System Pressurizer Relief Isolation No
?'
- Valve H0V-2536 Reactor Coolant System Pressurizer Relief Isolation No Valve MOV-21158 Charging Pump Suction from Refueling Water Storage No 1
Tank H0V-2115C Charging Pump Suction from Volume Control Tank No q
MOV-2115D Charging Pump Suction from Refueling Water Storage No 1
Tank MOV-2115E Charging Pump Suction from Volume Control Tank No MOV-2286A Charging Pump A Discharge No MOV-2287A Charging Pump A Alternate Discharge No 4
MOV-2286B Charging Pump B Discharge No MOV-2287B Charging Pump B Alternate Discharge No MOV-2286C Charging Pump C Discharge No MOV-2287C Charging Pump C Alternate Discharge No MOV-2289A Charging Pumps Discharge Line Stop Valve No MOV-2289B Charging Pumps Discharge Line Stop Valve No MOV-2373 Charging Pumps Recirculation Stop Valve No MOV-2275A Charging Pump A Recirc. Stop Valve No MOV-2275B Charging Pump B Recire. Stop Valve No MOV-2275C Charging Pump C Recire. Stop Valve No M0V-2350 Emergency Borate Valve No MOV-2370 Charging Pump to Seal Water Recire. Stop Valve No MOV-2836 High Head Cold Leg Safety Injection Isolation Valve No MOV-2869A Charging Pump Discharge Header Safety Injection No Stop Valve 1
MOV-2869B Charging Pump Discharge Header Safety Injection No Stop Valve MOV-2267A Charging Pump A Suction Valve (VCT)
No MOV-2267B Charging Pump A Suction Valve (LHSI)
No I
MOV-2269A Charging Pump B Suction Valve (VCT)
No j
H0V-2269B Charging Pump B Suction Valve (LHSI)
No i
MOV-2270A Charging Pump C Suction Valve (VCT)
No 1
MOV-2270B Charging Pump C Suction Valve (LHSI)
No MOV-2860A Low Head Safety Injection Pump A Suction Valve No MOV-2860B Low Head Safety Injection Pump B Suction Valve No 1
MOV-2862A Low Head Safety Injection Pump A Suction Valve No
.)
J MOV-28628 Low Head Safety Injection Pump B Suction Valve No l
i 1
NORTH ANNA - UNIT 2 3/4 8-24 Amendment No. 76 1
j
I g
=
t l
TABLE 3.8-2 (Continued)
HOTOR-OPERATED VALVES-THERMAL OVERLOAD PROTEC i
AN0/0R BYPASS DEVICES 3
Bypass Device Function Valve Number No l
Low Head Safety Injection Pump A Discharge to MOV-2863A Charging Pumps No l
Low Head Safety Injection Pump B Discharge to MOV-2863B Charging Pumps No l
Low Head Safety Injection Pump A Discharge Valve No MOV-2864A Low Head Safety Injection Pump B Discharge Valve l
MOV-2864B No Low Head Safety Injection Pump A Rec. Valve No MOV-2885A Low Head Safety Injection Pump B Rec.. Valve No MOV-2885B Low Head Safety Injection. Pump A Recirc. Valve No MOV-2885C Low Head Safety Injection Pump B Recire. Valve No MOV-28850 Low Head Safety Injection Pump A Discharge Line MOV-2890A Stop Valve No Low Head Safety Injection Pump B Discharge Line MOV-2890B
}
Stop Valve
?
MOV-2890C Low Head Safety Injection Pump Discharge Line No Stop Valve l;
Low Head Safety Injection Pump Discharge Line No ll MOV-28900 Stop Valve No i
Boron Injection Tank Inlet Valve No lj POV-2867A Boron Injection Tank Inlet Valve No MOV-28678
'R Boron Injection Tank Inlet Valve No MOV-2867C MOV-2867D Boron. Injection Tank Inlet Valve No MOV-2865A Accumulator Tank Discharge Valve No MOV-2865B Accumulator Tank Discharge Valve No MOV-2865C Accumulator Tank Discharge Valve l
h
- ll I
i l
l' d
- h-5 I
Amendment No. 76 I
NORTH ANNA - UNIT 2 3/4 8-25 t
c-. -.
-w am
, w:..ma.x 2:mw: mm e:.e=w.ww.w:.
l E
c I
PLANT SYSTEMS I
BASES d
3 l
SEALED SOURCE CONTAMINATIO_N 3/4.7.11 h
total body or individual organ irradiation d l
ble limits in The limitations j
the event of ingestion or inhalation of the sourc including alpha i
Leakage of sources emitters, is based on 10 CFR 70.39(c) limits for plutonium.
i t less than one 2
excluded from the requirements of this specification represen h
urce ta-maximum permissible body burden for total body irradiation i s
j rate terial is inhaled or ingested. groups according to their use
)/l Those sources which i
with the probability of damage to a source in that group.
those which are frequently handled are required to be tested m
!B jl boron measuring mechanism (i.e., sealed sources within radiatio jp are not.
h g.,
!d removed from the shielded mechanism.
'6 g
L SETTLEMENT OF CLASS 1 STRUCTURES 3/4.7.12 5[
program has been established to conduc f
( 1, The first survey was conducted in i
points at the site on a semiannual basis.
Where May 1976 to establish baseline elevations for most of the po t to the applicable, the baseline elevations of points established sub j
i f
May 1976 survey have been adjusted to the May 1976
- ! j nearby
~
the settlement records of settlement points on the same struc J
Baseline elevations for points established on dat
.j' v
structures.
May 1976 are indicated in Table 3.7-5.The determination of the
(
the precise leveling with second order Class II accuracy as de 1
semiannually.
i U.S. Department of Commerce National Oceanic and h ll be National Ocean Survey, 1974.1s inaccessible during a survey 4
t based on settlement of other points on the same structur 4
When any settlement point listed in l
Table 3.7-5 is dislocated or replaced, a documented rev having similar foundation conditions.
g b
records of points on the same structure and j
f ce a
the elevation for the point that reflects the estimated settlement s
}
If the total settlement or differential settle 3
75 percent of the allowable value, the frequency of sur 1
baseline survey.
Measurements of certain j
increased as dictated by the engineerin review. east once per 31 days for the f points are required to be performed atfive years of fa j
2 l
5 3/4 7-7 l
NORTH ANNA - UNIT 2 3v
s.: n. m : :;.:. myam..m w.w.c.u c c...:.:
a.n
. x..m.,.:.<..:. n.. m.u x.a.c., w :
\\
+
PLANT SYSTEMS o'l BASES
\\
3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES (Continued)
Allowable differential movement is controlled by pipe deflections permitted by fixation points in buildings. The items limiting differential settlement are as follows:
Reference Monitoring Points Limiting Item a
Containment Unit 2 Fuel Building Fuel Transfer Tube Containment Unit 2 Auxiliary Building 3"-SI-417 Containment Unit 2 Unit 2 Safeguards Area 6"-RH-418 Containment Unit 2 Unit 2 Main Steam Valve House 6"-SI-416
~ Containment Unit 2 Service Building (E-15) 16"-WFPD-409 l
Safeguards Area Unit 2 Unit 2 Main Steam Valve House 24"-WS-426 Auxiliary Building Unit 2 Main Steam Valve House 8"-5I-440 Auxiliary Building Fuel Building 4"-RP-28 Auxiliary Building Service Building Tunnel 24"-WS-102 Service Building (E-5, E-6)
Unit 1 Main Steam Valve House 24"-WS-26-151-Q3 Service Building (E-14) Unit 2 Main Steam Valve House 24"-WS-426-151-Q3 Auxiliary Feedwater 6"-WCMU-412-151-Q3 Pump House Unit 2 Pipe Tunnel l
Decontamination Building Pipe Tunnel 3"-CC-90-151-Q3 Fuel Building Waste Gas Decay Tank Enclosure 4"-GW-30-154-Q3 Safeguards Area Unit 2 Unit 2 Casing Cooling Building 6"-RS-455-153A-Q3 Service Water Pump House Service Water Piping 9 SWPH Expansion Joint Service Water Pump House Pipe Hanger in Reservoir 24"-WS-11-151-Q3 Service Water Pump House Service Water Pump House Mat The items limiting total settlement of structures are as follows:
Ij Monitoring Points Limiting Items 1
)
Service Water Piping 9 SWPH 36"-WS-1-151-Q3 Service Water Piping Expansion Joint Circulating Water Intake Structure
[j Turbine Building (B-9 1/2) 24"-WS-425-151-Q3 Service Building (E-17) 36"-WS-1-151-Q3 1
Fuel Oil Pump House 2 1/2"-F0F-151-5 Boron Recovery Tank Dike No settlement expected; settlement in excess of 0.03 feet would indicate an abnormality, 32 1/4"-WS-D84-151-Q3 i
Service Water Valve House 36"-WS-1-151-Q3 j
Service Water Tie-in Vault I
i NORTH ANNA - UNIT 2 B 3/4 7-8 Amendment No. 76 1
2