ML20086K489
| ML20086K489 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/04/1991 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086K492 | List: |
| References | |
| NUDOCS 9112130138 | |
| Download: ML20086K489 (10) | |
Text
_ _ - _ _ _ _ - _ _ _ _ _ _ _ _ - _.
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o, UNITED STATES i
NUCLE AR REGULATORY COMMISSION
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VIRGINTA ELECTRIC AhJ POWER COMPANY OLD 00t11t!10H ELECTRIC COOPERATIVE DOCKET t10. 50-338 NORTH ANNA POWER STATION, UNIT tJ0.1 AMEN 0 MENT TO FACILITY OPERATitlG LICENSE Amendment 110. 151 License No. PPF-4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated October 3, 1991, 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 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 Comission's regulations; D.
The issuance of this amendmant will not be inimical to the comon defense and security or tc 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 have been satisfied.
9112130138 911204 PDR ADOCK 05000338 p
2.
Accordingly, the license is t.rnended by changes to the Technical Speci-ficatons as indicated in the attachroent to this license amendt.cnt, and paragraph 2.D.(2) of f acility 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. 151, 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 the date of issuance and shall be iraplemented within 30 days.
FOR THE IltICLEAR REGULATORY COMMILSION 1
Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1991
o e
4 ATTACH!'.ENT TO LICENSE AMEN 0 MENT NO.
151 TO FACILITY OPERATING LICCHSE NO. NPF-4 DOCKET f40. 50-338 Replace the following page of the Appendix "A" Technical Specifications with the ericlosed page as indicated. The revised page is identified by amendment number and coritains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
paae 37%~4-13
. ~-- -
i REACTORCOOLANTSYSTBA SURVEILLANCE REQUAEMENT (Continued) 9.
Preservice insoection means an inspection of the fulllength of each tube in each steam generator performed by eddy current techniques prior to ser ece to establish a baseline condition of the tubing. This inspection F.t:l be performed using the equipment and techniques expected to be used l
during subsequent inse.wice inspection.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through. wall cracks) required by Table 4.4 2.
4.4.5.5 Renorts a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days, b.
The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which this inspection was completed. This report shall include:
1.
Number and extent of tubes inspected.
2.
Location and percent of wall-thickness penetration for each indicativn of an imr rhetion.
3.
Identification of tubes plugged.
c.
Results of steam generator tube inspections which fallinto Category C-3 require prompt notification of the Commission pursuant to Section 50.72 to 10 CFR Part 50. A Ucensee Event Report shall be submitted pursuant to Section 50.73 to 10 CFR Part 50 and shall provide a description of invehtigations conducted teatermine cause of the tube degrada'. ion and corrective measures taken to prevent recurrence.
l l
NORTH ANNA UNIT 1 3/4 4-13 Amendment No. E,63, 151
=
54 x
g TABLE 4.4-1 s
MINIMUM NUMBER OF STEAM GENERATORS TO BE e
C5 INSPECTED DURING INSERVICE INSPECTION
-a a
Preservice inspection No Yes Twoll No. of Steam Generators per Unit Three Four Two Three Four M
First inservice Inspection All One Two Two l
l 2
3 Second & Subsequent inservice inspections One One One One Table Notation:
- 1. The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the number of steam generators in tne plant) if the results of the first or previous inspections indicate that all steam generators are performing in a like manner. Note that under some circumstances. the operat...g conditions in one or more steam generators may be found to be more severe than those in other steam generators. Und-r such circum-stances the sample sequence shall be modified to inspect the most severe conditions.
- 2. The other steam generator not ir"pected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in 1 above.
- 3. Each of the other two steam generators not inspected during the first inservice inspections shael be inspected during the second and third inspections. The fourth and subsequent inspections shall follow the instructions described in 1 above.
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'o UNITED STATES
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~,j NUCLE AR REGULATORY COMMISSION r,
- e-WASHINGTON, D. C 20$55
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VIRGINTA ELECTRIC AND POWER COMPANY OLD DOMINION El_ECTRIC COOPERATIVE Dr'O ' NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 135 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.-
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated October 3, 1991, 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; a
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 cont acted in compliance with the Comission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.
t 4
- 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.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as f ollows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 135, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective u of the date of issuance shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COPMISSION He ert N. Berkow Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 4, 1991 i
t
1 ATTACHMENT TO LICENSE AMENDMENT NO. Sw TO FACILITY OPERATING LICDtSE NO. NPF-7 DOCKET NO. 50-339 Peplace the following page of the Appendix "A* Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
Pace F 4-13
4 REACTORCOOUMSWTBA SURVElLLANCE REQUIREMENT (Continued) 9.
Preservice Insoection means an inspection of the fulllength of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed using the equipment and techniques expected to be used l
during subsequent inservice inspection, b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4 2.
4.4.5.5 Reoorts a.
Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.
6.
The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which this inspection was completed. This report shall include:
1.
Number and extent of tubes inspected.
2.
l.ccation and percent of wall thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged.
c.
Results of steam generator tube inspections which fallinto Category C-3 require prompt notification of the Commission pursuant to Section 50.72 to 10 CFR Part 50. A Ucensee Event Report shall be submitted pursuant to Section 50.73 to 10 CFR Part 50 and shall provide a description of investigations.
conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
NORTH ANNA UNIT 2 3/4 4 13 Amendment No. U, $35
84 x
g TABLE 4.4-1 5
MINIMUM NUMBER OF STEAM GENERATORS TO BE C
jzi INSPECTED DURING INSERVICE INSPECTION
-4 N
Preservice lospection No Yes No. of Steam Generators per Unit Two Three Four Two Three Four M
First inservice inspection All One Two Two k
Second & Subsequent inservice Inspections One One One One l
l 2
3 Table Notation:
- 1. The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the results of the first or previous inspections indicate that all steam generators are, performing in a like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators. Under such circum-stances tlie sample sequence shall be modified to inspect the most severe conditions.
- 2. The other steam generator not inspected during the first inwrvice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in 1 above.
- 3. Each of the other two steam generators not inspected during the first inservice inspections shall be inspected during the second and third inspections. The fourth and subsequent inspections shall follow the instructions described in 1 above.
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