ML20004D311
| ML20004D311 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/28/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004D306 | List: |
| References | |
| NUDOCS 8106090144 | |
| Download: ML20004D311 (6) | |
Text
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o UNITED STATES NUCLEAR REGULATORY COMMISSION n
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W ASHINGTON, D. C. 20555
%,.....f SAFETY EVALUATION BY THE OFFICE OF
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fiUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 31 TO LICENSE NO. NPF-4 (VIRGINIA ELECTRIC A.D POWER COMPANY)
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Introduction:==
The NRC staff has completed a " consistency check" of Facility Operating License NPF-4 for the. North Anna Power Station, Unit No. 1.
The purpose of the check was to evaluate the present status of the license for timeliness of content based on a series of previous licensing actions (Amendments).
A brief chronology of License NPF-4 is provided below:
License NPF-4, issued November 26, 1977 to the Virginia Electric and Power Company (the licensee) for the North Anna Power Station, Unit No. 1 (NA-1) authorized the licensee to load nuclear fuel and maintain the facility in Mode 5 (cold shutdown) in accordance with the Technical Specifications
( Appendix A&B) of the license.
Initial fuel loading operations by the licensee commenced on November 27, 1977 and were completed on December 2, 1977.
On January 26, 1978, Amendment No. I to License NPF-4 was issued which authorized the licensee to operate NA-1 in Mode 3 (Hot Standby).
On " arch 17, 1978, Amendment No. 2 to License NPF-4 was issued which authorized cer cain exemptions to the NA-1 Technical Specifications in order to allow heat-up and simultaneous testing in Mode 3.
L On April 1, 1978, Amendment No. 3 to License NPF-4 was issued which revised in its entirety License NPF-4 and authorized the licensee to operate NA-1 at a full power level not in excess of 2775 megawatts thermal (100%).
On April 5, 1978, NA-1 achieved initici criticality, and on June 6, 1978, NA-1 was declared commercial.
Since initial criticality, NA-1 has completed two cycles of power operation and two refueling cycles.
The first refueling outage occurred during the period of October 1979 to January 1980.
The second refueling outage occurred during the period of January 1981 to early-April 1981.
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. NA-1 is presently in its third cycle (18 months) of power operations and the third refueling outage is now scheduled for early June 1982 to late July 1982.
Since initial issuance of License NPF-4, a large number of licensee corditions have been completed and deleted from the license by amendments. And, various amendments to the license have resulted in new or revised conditions to the Also, various exemptions to the NA-1 Technical Specifications were license.
issued to allow heatup and the completion of required testing prior to initial criticality.
Finally, in some instances exemptions to the Technical Speci-fications were permitted for a given period of time to allow the licensee to modify procedures for conformance with new NRC requirements.
In all of the Amendments, safety evaluations have been issued which serve as a basis for the respective Amendment licensing action except in several instances where the changes were of an administrative nature or where actions required the withholding of information from public disclosure in accordance with the provisions of 10 CFR 2.790(d).
Therefore, since these stipulations na longer servi any useful purpose, they are being removed from License dPF-4, as amended.
This action will facilitate identifying currently existing licensing conditions and will provide consistency and continuity for the present and future status of License NPF-4. These administrative actions are indicated below.
Discussion and Evaluation:
License Condition 2.D.l.(a)
Licensing Condition 2.D.l.(a) present states; "The licensee is authorized s
to operate the North Anna Power Station, Unit No. I at reactor core power levels not in excess of 2775 megawatts (thermal). Prior to entry in Mode 2 for initial the Virginia Electric and Power Con.pany shall comply with the criticality, construction items listed in Attachment 1."
Amendment No. 3, issued April 1, 1978, temporarily restricted NA-1 to Mode 3 (Hot Standby) until the completion of construction related items defined in to the license. These actions have been complated and Sentence 2 to License Condition 2.D.I.(a) and Attachment I to License NPF-4, as amended, are hereby removed.
Technical Specifications (TS) 2.D.2.(a)
Amendment No. 3 (April 1, 1978), incorporated conditions for operation and surveillance requirements for existing fire protection systems and admini-strative controls in the Appendix A Technical Specifications.
Condition l
. 2.0.2.(a) exempted the licensee from TS 4.3.3.7.1; 4.3.3.7.2; 4.3.3.7.3; 4.7.14.1.1; 4.7.14.1.2; 4.7.14.1.3; 4.7.14.2; 4.7.14.3; 4.7.14.4; 4.7.14.5 and 4.7.15 for a 30 day period of time effective from the date of issuance of Amendment No. 3 to License NPF-4.
The 30 day exemption was provided so that the licensee could modify plant procedures to conform to the details of the Appendix A Technical Specifications. This exemption is no ionger applicable and compliance with the Appendix A Technical Specifications has been enforced since May 1, 1978. Therefore, Condition 2.D 2.(a) is hereby removed from License NPF-4, as amended.
2.D.2.(b)
Condition 2.D.2.(b) (Amenoment No. 3-April 1, 1978) exempted the licensee from compliance with Appendix A Technical Specifications 4.6.4.3.c; 4.7.7.1.c; and 4.7.8.1.c applying to charcoal testing until (1) the first regularly scheduled refueling outage, or (2) the currently installed charcoal is replaced, whichever occurs first.
The charcoal was replaced pricr to startup after the first refueling outage and comiliance with Appendix A Technical Specifications 4.6.4.3.c; 4.7.7.1.c; and 4.7.8.1.c has been in effect since January, 1980. Therefore, Condition 2.D.2 (b) is no longer applicable and is hereby removed from License NPF-4.
2.D.2.(c)
Condition 2.0.2.(c), (Amendment No. 3, April 1, 1978) exempted the licensee from compliance with the Appendix A Technical Specifications 3.5.2.b; 4.5.2.e.2.b; 4.5.2.f.2; 3.5.3.b; and 4.0.5.a.1 as applicable to inservice inspection and testing of the Low Head Safety Injection Pumps prior to initial criticality only. The exemption is no longer applicable. Compliance with the Appendix A Technical Specifications has been enforced since initial criticality, April 5, 1978. Therefore, Condition 2.D.2.(c) is hereby removed from the license NPF-4, as amended.
2.D.2.(d)
Condition 2.D.2.(c) Amendment No. 2, March 17, 1978) modifi he Appendix A Technical Specifications 3.5.2.c; 4.5.2.a; and 3.5.3.c so t t a series of tests could be performed on both the recirculation spray p.nps and low head safety injection pumps to verify net positivo suction head requirements and long-term reliability of the pumps. Condition 2.D.2.(c) was renumbered Condition 2.D.2.(d) when License NPF-4 was revised in its entirety by Amendment No. 3 (April 1, 1978) to reflect full power authorization. Also, Condition 2.D.2.(c) as renumbered and revised to Condition 2.D.2.(d) stipulated that the modified Appendix A Technical Specifications were applicable to plant operations prior to initial criticality only. On April 5, 1978 NA-1 achieved initial criticality and the unmodified Appendix A Technical Speci-fications 3.5.2.c; 4.5.2.a; and 3.5.3.c for full power operations became effective. Therefore, Condition 2.D.2.(d) is no longer effective or applicable and is hereby removed.
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e 4.2.(e) tundition 2.D.?.(d), (Amendment No. 2, March 17, 1978) exempted the licensee 1
from compliance with the Appendix A Technical Specifications 3.6.2.2; 4.6.2.2.b; 4.0.5.a.1; and 4.6.3.1.3.
The exemptions permitted heatup and tests to be conducted simultaneously with the reinstallation of the outside recirculation spray pumps. Condition 2.D.2.(d), Amendment No. 2 was renumbered as Condition 2.D.2.(e) on issuance of Amendment No. 3 (April 1, 1978) and was revised to stipulate that the exemptions were applicable to plant operations prior to initial criticality only. On April 5, 1Sio NA-1 achieved initial criticality and the appropriate Appendix A Technical Specifications for full power operations became effective.
Therefore, Condition 2.D.2.(c) l'
-is h longer applicable and is hereby removed.
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Condition 2.D.(3)_f Condition 2.0.(3)f first issued in Amendment No. 3 (April 1 1978) stipulated thatpriortostartupafterthefirstrefuelingoutagetheIlcenseeshall implement the Administraive Procedures, Controls, and Fire Brigade Program and the Quality Assurance Program for the NA-1 Fire Protection Program. Also, the licensee was required to implement fire protection modifications prior to startup followirg the second refueling outage.
On March 6, 1979, Amendment No. 8 was issued to License NPF-4 which required the implementation of the fire protection program prior to restart following the second refueling outage in accordance with the NRC enclosed Safety Evaluation Report, " Fire Protection Program for North Anna Power Station, Units 1 and 2".
Condition 2.D.3.(f) as stated in Amendment No. 3 was revised to include these changes.
On December 21, 1979, during the first refueling outage, the Administrative Procedures, Controls, and Fire Brigade Program and Quality Assurance Program were implemented at NA-1.
And, prior to entry into Mode 4 (Cold Standby) after the second refueling outage, the licensee verified that all required fire protection modifications had been implemented to assure plant operability.
Therefore, the stipulations of License Condition 2.D.(3)f having been implemented as required, License Condition 2.D.(3)f is no longer applicable and is hereby removed from License NPF-4.
Condision 2.D.(3)o On June 14, 1979, Amendment No. 8 was issued to License NPF-4 which amended the.llctnse to add Condition 2.0.(3)o concerning surveillance requirements I
of the emergency diesel generator batteries.
Condition 2.D.. :)a stipulated that the provisions of Technical Specification l
4.0.4 were not 9plicable to the performance of surveillance activities 1
associated with diesel generator Technical Specification 4.8.1.1.3 until completion of the initial surveillance interval associated with that speci-ticat W.
-S-i The initial surveillance intervals for Technical Specification 4.8.1.1.3a, b, c, and d, specified intervals of 7 days, 92 days, once per 18 months, and at least once per 60 months, respectively. The initial surveillance interval for Technical Specification 4.8.1.1.3.a; 4.8.1.1.3.b; and 4.8.1.1.3.c have been completed. The only initial surveillance interval not yet completed is Technical Specification 4.8.1.1.3.d which specifies that at least once per 60 months, during shutdown, the battery capacity is at least 80%
of the manufacturer's rating when subjected to a performance discharge test.
Therefore, Licensing Condit',on 2.0.(3)o is revised to read, "The provisions 4
of Specification 4.0.4 are not applicable to the performance of surveillance i
activities associated with diesel generator battery Technical Specification 4.8.l.l.3.d until the completion of the initial surveillance interval associated with that specification".
Condition 2.D.(3)p.
Amendment No. 13 (8/3/79) added Condition 2.D.(3)p to License NPF-4 which authorized a one-time extension of less than one month on (1) Reactor i
j Protection and Engineered Safety Features Response Time and (2) Safety Injection and Containment Depressurization Actuation Testing.
The end of i
the current surveillance period for Technical Specifications 4.3.1.1.3; 4.6.2.1.c; 4.6.2.2.1.c; 4.6.2.3.c; 4.6.3.1.2.a; 4.6.3.1.2.b; 4.7.4.1.d.2; 4.7.8.1.d.2; and 4.3.2.1.3 was extended to September 15, 1979 which was beyond the time limit specified in Technical Specification 4.0.2.a.
The request for this extension was predicted on an expected refueling outage start date of September 15, 1979.
Amendment No. 15 (9/14/79) revised Condition 2.D.(3)p to permit continued operation for an additional 20 days to October 5, 1979 without performing the surveillance which would otherwise be required as noted in Condition 2.D.(3)p.
In addition, Condition 2.D.(3)p stipulated that NA-1 could not be operated, in Modes 1, 2, 3, or 4 after October 5, 1979 until the surveillance require-ments specified in Condition 2.D.(3)p had been completed.
The surveillance testing specified in Condition 2.0.(3)p was completed.
during the first refueling outage (October 1979 to January 1980) and the
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provisions of Technical. Specification 4.0.2.a have been enforced since startup after the first refueling. Therefore, Condition 2.D.(3)p is no longer applicable and is hereby removed.
License Condition G.
License Condition G. to Facility Operating License NPF-4, issued f
November 26, 1977 stipulated that License NPF-4 was subject to the out-
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j come of the proceedings in the case of Natural Resources Defense Council-vs. Vermont Yankee Nuclear Corporation.
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. The case of Natural Resources Defense Council vs. Vermont Yankee Nuclear Corporation no longer has any bearing ou License NPF-4.
Also, License NPF-7 (NA-2) issued on August 21, 1980, does not include the stipulation-of License Condition G.
Therefore, License Condition G. is hereby removed from Facility Operating License NPF-4.
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Conclusions:==
This amendment is strictly administrative in nature and therefore does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from-the standpoint of environ-mental impact and pursuant to 10 CFR 551.5(d)(4) that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Since this amendment is administrative, it does not involve significant new safety infor.4ation of a type not considered by a previous Commission safety review of the facility.
It does not involve a significant decrease in the probability or consequences of an accident, does not involve a significant decrease in a safety margin, and therefore does not involve a significant hazards consideration. We have also concluded that there is reasonable assurance that the health and safety of the public will not be endangered by this action and that the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. Also, we reaffirm our conclusions as otherwise stated in our Safety Evaluation Report and its Supplements and our Safety Evaluation Reports supporting License Amendments to Facility Operating License NPF-4.
Dated: May 28, 1981
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