ML20118C114
| ML20118C114 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/05/1992 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118C115 | List: |
| References | |
| NUDOCS 9210090285 | |
| Download: ML20118C114 (17) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 110RTH ANNA POWfR STATION. UNIT NO.1 AMENDMENT TO FACillTY OPERATING LICENSE Amendment No.167 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated October 2, 1992 and supplemented by letters dated April 29 and August 24, 1992, complies with the j
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 (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 Commission'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 Commission's regulations and all applicable requirements have been satisfied.
9210090285 921005 PDR ADOCK 05000338 P
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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 2.0.(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.167, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as'of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Her ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: October 5.1992 i
I
...______._.-__._-_.,,__...___,-.._.._..a
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allACHMENT T0 llCENSE AMENDMENT NO, 167 TO FACILITY OPERATING LICENSE N0, 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 amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Paaes Insert Paoes 3/4 l-70 3/4 7-70 3/4 7-71 3/4 7-71 3/4 7-7E 3/4 7-72 B 3/4 7-7a B 3/4 7-7a B 3/4 7-8 B 3/4 7-8
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 Table 3.7-5.
APPLICABILITY:
ALL MODES ACTION:
With either the total settl6 ment of any structure or the differential a.
settlement of any structures exceeding 75 percent of the allowable settlemest, conduct an engineering review of field conditions and evaluate the consequences of additional settlement.
Submit a special report to the Commission pursuant 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.12.1 The total settlement of each Class I structure or the differential settlement between Class 1 structures listed in Table 3.7-5 shall be determined by measurement and calculation at least once per 6 months.
The accuracy of the measurements shall be in accordance with second-order Class II accuracy as defined by the U.S. Department of Comerce, National Oceanic and Atmospheric Administration, National Ocean Survey,1974 NORTH ANNA - UNIT 1 3/4 7 70 Anendment No.167,
2o TABLE 3.7-S 4*
3E ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETilEMENT FOR CLASS I STRUCTURES E
AL LOWABL E ALLOWABLE ITEM SETTLEE NT SETTLEMENT SETTLEMENT SETTLEENT TOTAL.
DIFFERENTIAL
[
MO.
POINT STRUCTURE P0lMT STRUCTURE / COMPONENT (FEET)
(FEET) 1 7 or 10 Service Wrter 17, 18 North Side of N/A 0.220 from 7/77 Pump House Expansfon Joint Service Water Piping at SWPH 2
117
- Service Building 113 Unit 2 Main Steam N/A 0.047 from 7/77 (E-14)
Valve House 3
17, 18 North Side of Expansfon Joint 0.660 from 8/78 N/A g
Service Water Piping at SWPH y
4 114 Service Building 0.146 from 5/76 N/A (E-17) 5 25, 26, Service Water 0.320 from 4/87 N/A 27, 28 Valve House i
6 29, 30 Service Water 0.120 from 4/87 N/A l
31, 32 Tle-in V6 ult i
Critical differential settlement is downward movement of Point 117 with respect to Point 113.
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THIS PAGE DELETED NORTH ANNA - UNIT 1 3/4 7-72 Amendment No. 167,
PLANT SYSTD_6
_ BASES 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES settlement values, a program has been established to conduct specified number of points at the site on a semi-annual basis.
The first survey was conducted in May 1976 to establish baseline elevations for most of the points.
Where applicable, the base-line elevations of points establisneo an evaluation of the settlement records of settlement points on th structure or on nearby structures.
established on dates other than May 1976 as indicated in Table 3.7-5. Baseline f
Additional surveys will be perfomed semi-annually.
The determination cf the L
elevation of the points located in the imediate vicinity of the Service Water Reserve:r shall be by precise leveling with second-order Class II accuracy as defined by the U.S. DeDartment of Ccenerce, National Oceanic and Atmosoheric Aaministration. National Ocean Survey, 1974 The change in elevation of points 113 and 117 in the main plant area shall be detemined by direct measurement from a single instrument set-up.
A difference in survey rod readings from the single set-up will establish an initial difference in elevation between the two points.
will determine if there is a change in the initial difference.indicatingSubsequent read additional differential mvement.
Because the differential mvement between points 113 and 117 have previously approached the allowable limit, the direct reading method will provide the most accurate data and will minimize random survey error associated with survey loops.
The direct reading method will involve equipment and will produce results that are comparable to second-order Class II accuracy.
The change in elevation for point 114, which has more margin between recorded settlement and the allowable limit, will be detemined by a shor'.
level loop from rock-founded reference monument J through the points, and back to the monument.
This loop will involve a minicum of set-ups and will be perfomed with second-order Class II accuracy. The loop will also include points 113 and 117 as a check against the direct reading method.
All settlements recorded by the direct reading method will continue to be referenced to the original baseline date for each point to maintain continuity.
When any settlement point listed in Table 3.7-5 is inaccessible during a survey, comparison to allowable settlement shall be based on settlement of other points on the stme structure or on nearty structures having similar foundation conditions.
When any settlement point listed in Table 3.7-5 is dislocated or replaced, a documented review of the settlement records of points on the same structure and additionally points on nearby structures having similar foundation conditions shall provide a new reference elevation for the point that reflects the estimated settlement since the base-line survey.
If the total settlement or differential settlement exceds 75 percent of the allowable value, the frequency of surveillance shall be increased as dictated bv the engineering review.
HORTH AFMA - UNIT 1 B 3/4 7 7a Amendment No.167,
l Allowable differential movement is controlled by pipe deflections permitted by fixation points in buildings.
The items limiting differential settlement are as follows:
Ites No.
Reference Monitoring Points
_ Limiting Item 1
Service Water Pump House Service Water Piping & SWPH Expansion Joint 2
Service Bldg. (E-14)
Unit 2 Ksin Steam Valve House 24"-WS-426, 42B, 434, 436-151-Q3 The items limiting total settlement of structures are as follows:
it>nitoring Points Limiting Item 3
Service Water Piping at SWPH "3"-WS-1,2-151-03 4
Service Building (E-17) 36"-WS-1,2,3,4-151-03 S
Service Water Yalve House 321" '. D84-151-03 6
Service Water Tie-in Vault 35"-WS-1,2-151-Q3 h
NORTH ANNA - UNIT 1-B 3/4 7-8 Amendment No.167,
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- N-o UNITED STATES i
i NUCLEAR REGULATORY COMMISSION o
WASHINGTON. D C. 20565 a
vlRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 147 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Ccmmission) has found that:
A.
The application for amendment by Virginia Electric and Power Co..rsny et al., (the licensee) dated October 2,1989 and supplemented by letters dated April 29 and August 24, 1992, 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 pro 'isions of the Act, and the rules and regulations of the Comnossion; i
l C.
There is reasonable assurance (i) that the activities authorized by l
this amendment can be conducted without endangering the health and l
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
D.
The issuance of this amen ant will not be inimical to the common defense and security or to the health and safety af the public; and l
E.
The issuance of this amendmeat is in accordance with 10 CFR Part 51 l
of the Commission's regulations.ad all applicable requirements have been satisfied.
l l
I l
l l
l
2-2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this-license amendment, and paragraph 2.0,(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Specifications The= Technical Specifications contained in Appendices A and B, as t-revised through Amendment Na. 147 are hereby incorporated in the license. The licensee sitil operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/
W erbert N. Ber ow, Director Project Directorate 11-2 Division of Reactor Projects - I/II uffice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: october 5,1992 s
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-3 ATTACHMENT TO LICENSE AMEN 0 MENT NO. 147 TO FACillTY OPERATING LICENSE NO. NPF-7 l
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 contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Paaet insert Paaes 3/4 7-53 3/4 7-53 3/4 7-54 3/4 7-54 3/4 7-55 3/4 7-55 3/4 7 3/4 7-56 B 3/4 7-7 8 3/4 7-7 8 3/4 7-8 B 3/4 7-8 4
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PLANT SYSTEMS 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES l
LIMITING CONDITION FOR OPERATION 3.7c12.1 The total settlement of each Class I structure or the dioferential i
settlement between Class I structures shall not exceed the allowable v Table 3.7-5.
APPLICABILI~
' MODES ACTION:
With either the total settlement of any structure or the differential a.
settlenent of any structures exceeding 75 percent of the allowable
- tttlement, conduct an engineering review of field conditions and evaluate the consequences of additional settlerent.
Submit a special report to the Commission pursuant 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS 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 by measurement and calculation at least once per 6 months.
The accuracy of the measurement shall be in accordance with second-order Class II accuracy as defined by the U.S. Department of Commerce, National Oceanic and Atmospheric Administration, National Ocean Survey,1974 l
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HORTH ANNA e UNIT 2 3/4 7-53 Amendment No.147,
l TABLE 3.7-5 h
ALLOWABLE TOTAL SETTLEMENT OR DIFFERENTIAL SETTLEENT FOR CLASS I STRUCTURE Y
h l
ALLOWABLE ALLOWABLE TOTAL DIFFERENTIAL i
(TEM SETTLEENT SETTLEE NT SETTLEMENT SETTLEE NT g
NO.
POINT STRUCTURE POINT STRUCTURE /COPPONENT (FEET)
(FEET)
G 1
117
- Service Buildino 113 Unit 2 Main Steam N/A 0.047 from 7/77 u
(E 14)
Valve 11ouse 2
7 or 10 Service Water 17,18 Service Water Piping N/A 0.220 from 7/77 Pianp House at SWPH North Side of Expansion Joint 3
17, 18 Service Water 0.660 from 8/78 N/A Piping at SWPli R
North 'ide of Expaasion Jofrt I
4 116
- Service Building 0.167 from 5/76 N/A (E-15) 5 114 Service Building 0.146 frcm 5/76 N/A (E-17) 6 25,26 Service Water 0.320 from 4/87 N/A 27,28 Valve House 7
29,30 Service Water 0.120 from 4/87 N/A 31,32 Tie-in Vault I
Critical differential settlement is downward movement of Point 117 with respect g
to Point 113.
f Critical total settlement is downward movement of point 116 with respect to Unit 2 containment which is rock-founded.
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THIS PAGE DELETED l
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NORTH ANNA - UNIT 2 3/4 7-55 Amendment No. 147, -
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THIS PAGE DELElED NORTH ANNA - UNIT 2 3/4756 Amendment No.147,
l BASES 3/4.7.11 SEALED SOURCE CONTAMINATION The limitations on sealed source removable contamination ensure that the total body or individual organ irradiation does not exceed allwable limits in the event of ingestion or inhalation of the source material.
The limitations on removable contamination for sources requiring leak testing, including alpha esitters, is based on 10 CFR 70.39(c) limits for plutonium.
Leakage of sources excluded from the requirements of this specification mpresent less than one, maximum pemissible body burden for total taty irradiation if the source se terial is inhaled or ingested.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tast4J more often than those which are not.
Sealed sources which are continuoc ly enclosed within a shielded mechanism (i.e., sealed scurces within radiauon monitoring or boren measuring devices) are considered to be stored and need not be tasted unless they are removed from the shielded mechanisa.
3/4.7.12 SETTLEMENT 0F CLASS 1 STRUCTURES In order to assure that settlemest does not exceed predicted and allowable settlement values, a program has been established to conduct a survey of a specified nuroer of points at the site on a semi-annual basis.
The first survey was conducted in May 1976 to establish baseline elevations for most of the points.
Where applicable, the base-line elevations of points establishee subsequent to the May 1976 survey have been adjusted to the May 1976 survey by an evaluation of the settlement records of settlement points on the same structure or on neart>y structures.
Baseline elevations for some points were i
established on dates other than Ny 1976 as indicated in Table 3.7-S.
I Additional surveys will be performed semi-annually.
The detemination of the elevation of the points located in the immediate vicinity of the Service Water Reservoir shall be by precise leveling with second-order Class II accuracy as oefined by the U.S. Deoartment of Commerce, National Oceanic and Atmosoberic Administration. hational Ocean Survey, 1974.
~
l The change in elevation of points 113 and 117 in the main plant area shall be determinee by direct measurement from a single instrument set-up.
A difference in survey rod readings from the Jingle set-up will establish an initial difference in elevation between the two points.
Subsequent readings will detertiine if there is a change in the initial difference, indicating additional differential movement.
Because the differential moveunt between points 113 and 117 have previously approached the allowable limit, the direct reading method will provide the ecst accurate data and will minimize rancom survey error associated with survey loops.
The direct reading inethod wili involve equipment and will produce results that are ccc: parable to second-orcer Class II accuracy.
NORTH ANNA - UNIT 2 8 3/4 7-7 Amendment No. %7,
i PLANT SYSTEMS BASES 3/a.7.12 SETTLEMENT OF CLASS 1 STRUCTURES (contfnued)
The change in elevation for points 114 and 116, which have more margin between recorded settlement and the allowable limit, will be determined by a short level loop from rock-founded reference monument J, through the points, and back to the monument.
This loop will involve a minimum of set-ups and will be perfonned with second order Class !! accuracy. The loop will also include points 113 and 117 as a check against the direct reading method.
All settlements recorded by the direct reading method will continue to be referenced to the original baseline date for each point to maintain continuity.
When any settlement point Ifsted in Table 3.7-5 is inaccessible during a survey, comparison to allowable settlement shall be based on settlement of other points on the same structure or on neartiy structures having similar foundation conditions.
When any settlement point listed in Table 3.7-5 is dislocated or replaced, a documented review of the settlement records of points on the same structure and additionally points on nearty structures having similar foundation conditions shall provide a new reference elevation for the point that reflects the estimated settlement since the t,ase-line survey.
If the total settlement or differential settlement exceeds 75 percent of the allowable value, the frequency of surveillance shall be ir. creased as dictated by the engineering review.
}
Allowable differential movement is controlled by pipe deflections permitted by fixation points in buildings.
The items linf ting differwrtial settlement are as follows:
Its No.
Referene!
Monitoring Points Limitinq I M l
1 l
Service Building (E-14) Unit 2 Main Steam Valve House 24"-WS-426,428 434, 436-151-Q3 2
l Service Water Pump Service Water Picing Expansion Joint House 9 SWPH The items limiting total settlement of strvetures are as follows:
l 8tmitoring Points
_Limitinq Itans Service 'iater Piping 9 SWPH 36"-WS-1,2-151-Q3 4
Service Building (E-15) 16*-WFPD-409,413,417 32*-SHP-401, 402, 403 5
Service Bufiding (E-17) 36*-WS-1,2,3,4-151-03 6
Service Watar Yalve House 321 *-WS-084-151-Q3 7
Service Water Tie-in Vault 36"-WS-1,2-151-03 NORTH ANNA - UNIT 2 B 3/4 7-8 Amendment No.147, l
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