Text

Amends 57 & 39 to License NPF-4 & NPF-7,respectively, Terminating Requirement to Measure Turbidity & Suspended Solids in Outflow of Drain Sys Under Water Pumphouse
	ML20091L330
Person / Time
Site:	North Anna
Issue date:	05/23/1984
From:	John Miller; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20091L333	List: ML20091L330; ML20091L335;
References
	NUDOCS 8406080016
	Download: ML20091L330 (22)
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UNITED STATES EY

,e NUCLEAR REGULATORY COMMISSION j,!

.,,E WASHING TON, D. C. 20555

\\..~.s l VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DCCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-4 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated September 16, 1983, 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 the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; 4

D.

The issuance of this amendment will not be inimical to the comon 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 Ccmission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 57, are hereby incorporated in the license. _The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i-~//'l 4'9

, 2-s e,.

James R. Miller, Chief

/

Operating Reactors Branch #3 Division of Licensing

Attachment:

. Changes to the Technical Specifications Date of Issuance: May 23, 1984 l

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.57 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 amemdment number and contains vertical lines indicating the area of change.

The. corresponding overleaf pages are also provided to maintain document completeness.

Paae 3/4 7-18 3/4 7-70 3/4 7-72 3/4 7-73 3/4 7-74 i

_5

PLANT SYSTEMS 3/4.7.3-COMP 0NENT COOLING WATER SUBSYSTEM LIMITING CONDITION FOR OPERATION 3.7.3.1 At least two component cooling water subsystems (shared with Unit 2) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one component cooling water subsystem OPERABLE, restore at least two subsystems to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.3.1 At least two component cooling water subsystems shall be demon-strated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power oparated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

NORTH ANNA - UNIT 1 3/4 7-17 a

PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two service water loops (shared with Unit 2) shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position, b.

At least once per 6 months by measurement of the movement of the pumphouse and wing walls, c.

At least once per 18 months during shutdown, by:

1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a safety iniection signal.

2.

Verifying that each containment isolation valve actuates to its correct position on a containment high-high signal.

NORTH ANNA - UNIT 1 3/4 7-18 Amendment No. 3,57

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1.

With a half-life greater than 30 days (excluding Hydrogen 3),and 2.

In any form other than gas.

b.

Stored sources-not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

c.

Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.11.1.3 Reports - A Special Report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of removable contamination.

NORTH ANNA -_ UNIT 1 3/4 7-69 Amendment No.16

PLANT SYSTEMS 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES LIMITING CONDITION FOR OPERATION 3.7.12.1 The total settlement of each Class 1 structure or the differential settlement between Class 1 structures shall not exceed the allowable values of Table 3.7-5.

APPLICABILITY: All MODES ACTION:

a.

With either the total settlement of any structure or the dif-ferential settlement of any structures exceeding 75 percent of the allowable settlement, conduct an engineering review of field conditions and evaluate the consequences of additional s ettlemen t.

Submit a special report to the Commission pur-suant to Specification 6.9.2 within 60 days, containing the results of the investigation, the evaluation of existing and possible continued settlement and the remedial action to be taken if any, including the date of the next survey.

b.

With the total settlement of any structure or the differential settlement of any two structures exceeding the allowable settlement value of Table 3.7-5, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.12.1 The total settlement of each Cla:s 1 structure or the dif-ferential settlement between Class 1 structures listed in Table 3.7-5 shall be determined to the nearest 0.01 foot by measurement and calcula-tion at least once per 6 months.

NORTH ANNA - UNIT 1 3/4 7-70

. Amendment No. #.57

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TABLE 3.7-5 g~

ALLOWA8tE TOTAL SETTLEENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES 1N' ALLOWABLE ALLOWABLE TOTAL DIFFERENTIAL

3..

SEITLEENT SETTLEMENT SETTLEE Nia SETTLEE NT*

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- POINT STRUCTURE POINT STRUCTURE /COOFONENT-(FEET)

(FEET)

,3 130 Containment Unit 1 223 fuel Sullding N/A 0.12

^"

g-130 Containment Unit 1 129 Auxiliary Building N/A 0.12

~-4 143 Containment Unit 1 '

142 Unit 1 Safeguards Area.

N/A.

0.04

'144 -

Contalement Unit 1 -

145 Unit 1 Safeguards Area N/A 0.04 149' Containment Unit l' 239 Unit 1 Main Steam Valve House

,N/A 0.12 144 Containment Unit 1 243.199.132 Service Building

- N/A 0.12 146

. Safeguards Unit 1 239 Unit 1 Main Steam Valve House N/A 0.07

.128

' Auxiliary Building 238 Unit 1 Main Steam Valve House N/A 0.08 y-129-Auxiliary Sullding 239 Unit 1 Main Steam Valve House N/A 0.08.

129

.l Auxiliary Building 223 Fuel Building N/A 0.05 123 Auxiliary Building-224 fuel Building N/A.

0.05 122' Auxiliary Building 119 Service Building Tunnel N/A 0.07 7 or 10 Service Water Pump House 15.16 North Side of Expansion Joint N/A 0.22 from 7/77 17,18 Service Water Piping at SWPH s'

243.132.

- Service Building (E-5. E-6) 238 Unit 1 Main Steam Valve House N/A 0.04 l'17

- Service Building (E-14) 113 Unit 2 Main Steam Valve House N/A 0.03 from 7/77 222 Auxiliary feedwater Pump House - Unit 1 248 Pipe Tunnel N/A 0.12 to E

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ALLOWABLE TOTAL SETTLEENT OR DIFFERENTIAL SETTLEENT FOR CLASS 1 STRUCTURES

.s ALLOWABLE ALLOWABLE c.

TOTAL DIFFERENTIAL

-z-

SETTLEMENT SETTLEE NT SETTLEMENT

SETTLEENT*

Q POINT STRUCTURE POINT STRUCTURE /COWONE NT (FEET)

(FEET) 15,16,17, North Side of Expansion Joint 0.22 from 8/78 M/A 18 Service Water Piping at SWPH 228

~ Decontamination Building 250 Pipe Tunnel r, A 0.06 226 Fuel Building 251 Weste Gas Decay Tank Enclosure N/A 0.06 8

Service Water Pump House H-569,H.584 Pipe llanger in Reservoir N/A 0.17 M

-114.

Service Building (E-17) 0.09 N/A a.

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.141 Safeguards Area - Unit 1 253 Unit 1. Casing Cooling Bldg.

N/A 0.12 from 2/79

.n lM-158

- - Turbine Butiding (B-91/2) 0.06 N/A

.245, 246 Fuel Oil Pump House' O.03 N/A 206,207 208,'209-Boron Recovery Tank Dike 0.03 N/A 204 Circulating Water Intake Structure 0.15 N/A T

Unless otherwise' indicated, allowatie settlements are from baseline elevations established in May 1976 or reference elevations corrected to the 4.'

May 1976 survey.

- Critical differential settlemert is downward ' movement of Point 117 with respect to Point 113.

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- - Not Class I structure, but settlements affects Class 1 pipeline.

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i PLANT SYSTEMS 3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR 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 beneatn tne pumphouse shall not exceed the values given in Table 3.7-6.

APPLICABILITY: All MODES.

ACTION:

With the groundwater level of the service water reservoir or the groundwater flow rate exceeding any of tha limits of Table 3.7-6, an engineering evalua-tion shall be performed by a Licensed Civil Engineer to determine the cause of the high ground water or flow rates and the influence on the stability of the service water reservoir and pumphouse. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days, containing the results of the evaluation and any corrective action determined to be necessary.

SURVEILLANCE REQUIREMENTS 4.7.13.1 The groundwater level within the dike of the service water reservoir as determined by monitoring the piezometers shall be within limits presented in Table 3.7-6.

Measurements shall be performed at least once per 6 months. The groundwater flow rate shall be determined 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 rate shall not exceed that established in Table 3.7-6.

A visual inspection of the clarity of the outflow from each drain shall be performed in conjunc-tion with the flow monitoring effort.

1 NORTH ANNA - UNIT 1 3/4 7-73 Amendment No. JZ,57

~M TABLE 3.7-6 ALLOWABLE GROUNDWATER LEVELS - SERVICE WATER RESERVOIR h

PIEZ0 METER PIEZ0 METER ALLOWABLE GROUNDWATER ELEVATION, z

NO.

LOCATION Mean Sea Level (feet) e 10 SE, toe 277 11 SWPH, (Units 1 & 2) crest 280 12 SWPH, (Units 1 & 2) toe 285 13 SWPH, (Units 1 & 2) crest 280 14 SWPH, (Units l'& 2) crest 280 15 SE, crest 280 16 SE, crest 280 17 SE, crest 280 18 SWPH (Units 3 & 4) 295 f

ALLOWABLE DRAIN FLOW RATE DRAIN OUTLETS LOCATION (gallons per minute) g k

1 through 6 Drainage Gallery FLOW RATE SHALL NOT EXCEED 8.5 GALLONS PER MINUTE (gpm) 2 e

6

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION 3

l wAsmNGTON, D. C. 20586 k.....,/

VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. NPF-7 1.

The Nuclear Regulatory Connission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated September 16, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conforinity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Consission's regulations; 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; and E.

The issuance of this amendment is in accordance with 10 CFR Part (

51 of the Connission's regulations and all applicable requirements) have been satisfied.

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2.

Accohlfa31y, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and. paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby

.amendea' to read as follows:

7 (2) TechnidalSpecifications

.sThe Technical Specifications contained in Appendices A and B,

,,as revised through Amer.dmant No. 39, are hereby incorporated in the license, The licensee shall operate the facility in accordance with the Tech.,1 cal Specifications.

3.

This license amendment is effective within 30 days from the date of issuance.

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!i 100. THE NUCLEAR REGULATORY COMMISSION

^'

nr James R. Miller, Chief

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Operating Reactorr 9 ranch #3 CA-

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Division of Licensing

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Attachment:

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s y Specifications

Date of Issuance:IAay23;1984,'[

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ATTACHMENT TO LICENSE AMENDMENT AMENDMEhT NO. 39 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contains vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document complateness.

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.P,agg 3/4 7-15 3/4 7-53 3/4 7-56 3/4 7-57 3/4 7-58 l

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i PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two service water loops (shared with Unit 1) shall be OPERABLE.

APPLICABILITY: MODES 1, 2,-3 and 4.

ACTION:

With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two service water loops shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.-

b.

At least once per 6 months by measurement of the movement of the pumphouse and wing walls.

y c.

At least once per 18 months during shutdown, by:

l 1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a safety injection signal.

2.

Verifying that each containment isolation valve actuates to its correct position on a containment

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high-high signal.

l NORTH ANNA -: UNIT 2 3/4 7-15 Amendment No. 39

PLANT SYSTEMS 3/4.7.5 ULTIMATE HEAT SINK LIMITING CONDITION FOR OPERATION 3.7.5.1 The ultimate heat sinks shall be OPERABLE:

a.

Service Water Reservoir with:

1.

A minimum water level at or above elevation 313 Mean Sea Level, USGS datum, and 2.

An average water temperature of less than or equal to 95'F as measured at the service water pump outlet.

b.

The North Anna Reservoir with:

1.

A minimum water level at or above elevation 244 Mean Sea Level, USGS datum, and 2.

An average water temperature of less than or equal to 95*F as measured at the condenser inlet.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.5.1 The ultimate heat sinks shall be determined OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the average water temperature and water level to be within their limits.

4.7.5.2 Data for calculating the leekage from the service water reservoir shall be obtained and recorded at least once per 6 months.

- NORTH ANNA - UNIT 2 3/4 7-16

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PLANT SYSTEMS 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES LIMITING CONDITION FOR OPERATION 3.7.12.1 The total settlement of each Class 1 structure or the differential settlement between Class 1 structures shall not exceed the allowable values of Table 3.7-5.

APPLICABILITY: All MODES ACTION:

a.

With either the total settlement of any structure or the differen-tial settlement of any structures exceeding 75 percent of the allowable settlement, conduct an engineering review of field conditions and evaluate the consequences of additional settlement.

Submit a special report to the Commission pursuant to Specifica-tion 6.9.2 within 60 days, containing the results of the investi-gation, the evaluation of existing and possible continued settle-ment and a remedial action to be taken if any, including the date of the next survey.

b.

With the total settlement of any structure or the differential settlement of any two structures exceeding the allowable settle-ment value of Table 3.7-5, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.7.12.1 The total settlement of each Class 1 structure or the differential settlement between Class 1 structures listed in Table 3.7-5 shall be deter-mined to the nearest 0.01 foot by measurement and calculation at least once per 6 months.

NORTH-ANNA - UNIT 2 3/4 7-53 Amendnent No. 39

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ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES ALLOWABLE ALLOWABLE e

TOTAL DIFFERENTIAL 5

SETTLEMENT SETTLEMENT SETTLEMENT

SETTLEMENT *

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POINT STRUCTURE P0 INT STRUCTURE / COMP 0NENT (FEET)

(FEET) 131 Containment Unit 2 224 Fuel Building N/A 0.12 131 Containment Unit 2 123 Auxiliary Building N/A 0.05 106 Containment Unit 2 105 Unit 2 Safeguards Area N/A 0.07 107 Containment Unit 2 108 Unit 2 Safeguards Area N/A 0.07 131 Containment Unit 2 124 Unit 2 Main Steam Valve House N/A 0.03 y

107 Containment Unit 2-116 Service Building (E-15)

N/A 0.12 111 Safeguards Area Unit 2 124 Unit 2 Main Steam Valve House N/A 0.12 7i 122 Auxiliary Building 120 Unit 2 Main Steam Valve House N/A 0.04 123 Auxiliary Building 124 Unit 2 Main Steam Valve House N/A 0.04 123 Auxiliary Building 224 Fuel Building N/A 0.05 129 Auxiliary Building 223 Fuel Building N/A 0.05 122 Auxiliary Building 119 Service Building Tunnel N/A 0.07 243, 132 Service Building 238 Unit 1 Main Steam Valve House N/A 0.04 (E-5,E-6) 117

- Service Building (E-14) 113 Unit 2 Main Steam Valve House N/A 0.03 from 7/77

.231 Auxiliary Feedwater Pump House Unit 2 249 Pipe Tunnel N/A 0.12 228 Decontamination Building 250 Pipe Tunnel N/A U.06

8

=

E TABLE 3.7-5 (Continued)

ALLOWABLE TOTAL SETTLEMENT OR OIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES E

ALLOWABLE ALLOWABLE Q.

TOTAL DIFFERENTIAL N

SETTLEMENT SETTLEMENT SETTLEMENT

SETTLEMENT

POINT STRUCTURE POINT

STRUCTURE /COMPpNENT (FEET)

(FEET)-

226 Fuel Building 251 Waste Gas Oecay Tank Enclosure N/A 0.06 104 Safeguards Area Unit 2 254 Unit 2 Casing Cooling Building N/A 0.12 from 2/79 3

7, 10

-Service Water Pump 15, 16, Service Water Piping at SWPH N/A 0.22 ly House 17, or 18 North Side of Expansion.loint from'7/77 E

8

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Service Water Pump House H-569 Pipe Hanger in Reservoir N/A 0.17 H-584 15,16, Service Water Piping at SWPH 0.22 from 8/78 N/A 17, 18 North Side of Expansion Joint 204 Circulating Water Intake 0.15 N/A Structure 158

'^^* Turbine Building 0.06 N/A (8-9 1/2) 114 Service Building (E-17) 0.09 N/A

'245, 246 Fuel Oil Pump House 0.03 N/A 206 207, Boron Recovery Tank Dike 0.03 N/A 208, 209 i

TABLE 3.7-5 (Continued)

$5 ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEMENT FOR CLASS 1 STRUCTURES

.:c 15 4-N

Unless otherwise indicated, allowable settlements are from base-line elevations established in May 1976 or reference elevations corrected to the May 1976 survey.

- Critical differential settlement is downward movement of Point 117 with respect to Point 113.

- - Not Class 1 structure, but settlement affects Class 1 pipeline.

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PLANT SYSTEMS 3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR LIMITING CONDITION FOR OPERATION 3.7.13 The groundwater level of the service water reservoir (common to Units 1 and 2) shall not exceed the elevation at the locations listed in Table 3.7-6.

The flow of croundwater from the drains beneath the pumphouse shall not exceed the values given in Table 3.7-6.

APPLICABILITY: All MODES.

i ACTION:

With the groundwater level of the service water reservoir or the ground water flow rate exceeding any of the limits of Table 3.7-6, t engineering evaluation shall be performed by a Licensed Civil Engineer to determine the cause of the high ground water or flow rates and the influence on the stability of the service water reservoir and pumphouse. A Special Report I

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 l

any corrective action determined to be necessary.

SURVEILLANCE REQUIREMENTS p.-

L 4.7.13.1 The groundwater level within the dike of the service water reservoir as determined by monitoring the piezometers shall be within limits presented in Table 3.7-6.

Measurements shall be performed at least once per 6 months. The groundwater flow rate shall be determined 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 rate shall not exceed that established in Table 3.7-6.

A visual inspection of the clarity of the outflow from each drain shall be performed in conjunction with the flow monitoring effort.

I 4

NORTH ANNA - UNIT 2 3/4 7-57 Amendment No. 39 t

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TABLE 3.7-6 3

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ALLOWABLE GROUNDWATER LEVELS - SERVICE WATER RESERVOIR l

2; PIEZ0 HETER PIEZ0 METER ALLOWABLE GROUNDWATER ELEVATION NO.

LOCATION Mean Sea Level (feet) 10 SE,. toe 277

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

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' - 15 SE, crest 280

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'16 SE, crest 280 E

17' SE, crest 280 18 SWPH (Units 3 & 4) 295 ALLOWABLE DRAIN FLOWRATE DRAIN OUTLETS' LOCATION (gallons per minute) l-1 through 6 Drainage Gallery FLOW RATE SHA.LL NOT EXCEED sj 8.5 GALLONS PER MINUTE (gpm) 4

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ML20091L330

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