ML020800601
| ML020800601 | |
| Person / Time | |
|---|---|
| Site: | North Anna  (NPF-007) |
| Issue date: | 03/19/2002 |
| From: | Stephen Monarque NRC/NRR/DLPM/LPD2 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| Monarque S, NRR/DLPM, 415-1544 | |
| References | |
| TAC MB0962 | |
| Download: ML020800601 (20) | |
Text
March 19, 2002 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060
SUBJECT:
NORTH ANNA POWER STATION, UNIT 2 - ISSUANCE OF AMENDMENT RE:
PROPOSED OPERATING LICENSE CHANGES - DELETION OF OBSOLETE LICENSE CONDITIONS (TAC NO. MB0962)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 211 to Facility Operating License (FOL) No. NPF-7 for the North Anna Power Station, Unit No. 2. The amendment changes the FOL in response to your letter dated January 9, 2001.
This amendment revises the FOL to remove expired license conditions, make editorial changes, relocate license conditions, and remove license conditions associated with completed modifications.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Stephen R. Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-339
Enclosures:
- 1. Amendment No. 211 to NPF-7
- 2. Safety Evaluation cc w/encls: See next page
Mr. David A. Christian March 19, 2002 Sr. Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060
SUBJECT:
NORTH ANNA POWER STATION, UNIT 2 - ISSUANCE OF AMENDMENT RE: PROPOSED OPERATING LICENSE CHANGES - DELETION OF OBSOLETE LICENSE CONDITIONS (TAC NO. MB0962)
Dear Mr. Christian:
The Commission has issued the enclosed Amendment No. 211 to Facility Operating License (FOL) No. NPF-7 for the North Anna Power Station, Unit No. 2. The amendment changes the FOL in response to your letter dated January 9, 2001.
This amendment revises the FOL to remove expired license conditions, make editorial changes, relocate license conditions, and remove license conditions associated with completed modifications.
A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Stephen R. Monarque, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-339
Enclosures:
- 1. Amendment No. 211 to NPF-7
- 2. Safety Evaluation cc w/encls: See next page Distribution:
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DATE 2/28/02 2/15/02 02/13/02 02/13/02 10/16/01 06/14/01 2/22/02 COPY Yes/No Yes/No Yes/No Yes/No Yes/No Yes/No Yes/No IRSB IOHS IOLB RORP SRXB OGC SC(A):PDII/SI KGibson**
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JHeck RLaufer 02/11/02 2/25/02 2/28/02 3/4/02 11/01/01 3/14/02 3/18/02 Yes/No Yes/No Yes/No Yes/No Yes/No Yes/No Yes/No OFFICIAL RECORD COPY
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. NPF-7 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 January 9, 2001, 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 (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. 2.
Accordingly, the license is amended by deleting existing Paragraphs 2.C.(2)(b), 2.C.(3)
through 2.C.(21), 2.C.(24), 2.D, 2.F, 2.G, 2.H, and 2.I, and Appendix C associated with the removal of obsolete license conditions. In addition, the following license paragraphs have been relocated to new license paragraphs: 2.C.(22) is now designated as 2.C.(4),
2.C.(23) is now designated as 2.D, 2.G is now designated as 2.C.(3)(a), 2.H is now designated as 2.C.(3)(a), 2.J is now designated as 2.F, and Appendix C is now designated as 2.C.(3)(b). A new license paragraph 2.C(5) was added.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Acting Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
License Pages Date of Issuance: March 19, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 211 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Facility Operating License with the enclosed pages as indicated. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages Insert Pages License Pages 1 through 13a License Pages 1 through 4 Appendix C
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 211 TO FACILITY OPERATING LICENSE NO. NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION, UNIT NO. 2 DOCKET NO. 50-339
1.0 INTRODUCTION
By application dated January 9, 2001, Virginia Electric and Power Company (VEPCO, the licensee) requested changes to Facility Operating License (FOL) No. NPF-7 for North Anna Power Station, Unit 2. This amendment revises the FOL to remove expired license conditions, relocate license conditions, and make editorial changes.
2.0 BACKGROUND
The licensee has proposed administrative changes to the North Anna Unit 2 FOL to remove those license conditions that no longer apply or relocate license conditions within the FOL to provide a more consistent and concise license format. These proposed changes are divided into four groups as follows:
- 1. Editorial changes to the FOL;
- 2. Relocation of existing FOL license conditions;
- 3. Removal of license conditions associated with completed modifications; and
- 4. Removal of expired license conditions in the FOL.
3.0 DISCUSSION AND EVALUATION The staff has addressed the licensees proposed changes to the FOL following the order in which they appear in the FOL.
Sections 1.B., 1.F, 1.H, and 1.I The licensee has proposed editorial changes in these FOL sections to correct the punctuation. These proposed changes to the FOL are acceptable.
2.A.
The licensee has proposed deleting the phrase amendment to the to facilitate concise reference to the revised document as the license. This proposed change to the North Anna Unit 2 FOL provides consistency and is acceptable.
The licensee has proposed that the references to the Final Safety Analysis Report (FSAR) be changed to the Updated Final Safety Analysis Report (UFSAR), and the phrase as supplemented and amended (Amendment Numbers 17 - 69) be deleted. Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.71(e) requires licensees to periodically update their FSAR. Thus, the UFSAR is understood to mean the most up-to-date version of the FSAR and no further identification via amendment numbers is necessary.
The licensees proposed change is acceptable.
2.B(1)
The licensee has proposed an editorial change in this FOL section to correct the punctuation. This proposed change to the FOL is acceptable.
2.B(2)
The licensee has proposed editorial changes to correct the punctuation. These proposed changes to the FOL are acceptable.
The licensee has proposed that the references to the FSAR be changed to the UFSAR, and the phrase as supplemented and amended be deleted. 10 CFR 50.71(e) requires licensees to periodically update their FSAR. Thus, the UFSAR is understood to mean the most up-to-date version of the FSAR and no further identification is necessary. The licensees proposed change is acceptable.
2.B(3), 2.B.(4), and 2.B(5)
The licensee has proposed editorial changes in these FOL sections to correct the punctuation. These proposed changes to the FOL are acceptable.
2.C(1)
The licensee has proposed capitalizing all letters in the phrase Vepco for consistency within the FOL. This proposed editorial change is acceptable.
2.C(2)
The licensee has proposed deleting the reference to Appendix B, Environmental Technical Specifications (ETS). License Amendment No. 31, dated May 5, 1983, removed Part I of the ETS and renamed it Part II of the Environmental Protection Plan (EPP). Due to this change, FOL Section 2.C(2) is no longer correctly stated. As an administrative correction, Section 2.C(2) will only refer to the Technical Specifications of Appendix A. A new section 2.C(5) is added to address the EPP contained in Appendix B. The proposed change to the FOL is acceptable.
2.C.(2)(b)
The licensee has proposed deleting this section. License Amendment No. 18, dated February 18, 1982, granted a one-time 2-week extension for the Unit 2 hydraulic snubber functional testing until the Spring 1982 refueling outage, which began on March 7, 1982. This license condition has expired. The licensees proposed change is acceptable.
2.C.(3)
The licensee has proposed to replace this current section. This current license condition applies to the Initial Startup Testing Program for Unit 2, which has been completed. This startup test program was based upon a series of letters and responses to the NRC during 1979. These letters are acknowledged in the review chronology of Supplement 10 of the North Anna Safety Evaluation Report (NUREG-0053). Testing was completed and the Reactor Startup Report was submitted to the staff on March 10, 1981. The licensees proposal to delete this current section is acceptable since the requirements have been met and the license condition is obsolete.
The licensee proposes to replace the current section with the following paragraph:
2.C(3) Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the condition or within the operational restrictions indicated.
The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission:
The licensees proposed change is acceptable.
2.C.(3)(a)
The licensee proposes to relocate FOL Section 2.G to this new section.
2.C.(3)(a) will read as follows:
If VEPCO plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Power Station, the NRC shall be notified in writing regardless of whether the change affects the amount of radioactivity in the effluents.
The licensee also proposes to relocate the modified FOL Section 2.H to this new section. The modification of FOL 2.H is discussed in 2.H. The relocated Section 2.H will read as follows:
VEPCO shall report any violations of this requirement within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate, no later than the first working day following the violation, with a written followup report within 14 days.
Relocation of these license conditions has no impact upon the technical aspects of the items being removed. The licensees proposed changes are acceptable.
2.C.(3)(b)
The licensee proposes to relocate the text of Appendix C, Additional Conditions, to this new section. Relocation of license conditions within the FOL has no impact upon the technical aspects of the item being removed. Currently, Section 2.I references FOL Appendix C. Appendix C was added by License Amendment No. 195, dated August 26, 1998. To construct a clean concise FOL document, the proposed change would move the single Appendix C requirement to within the existing Additional Conditions section of 2.C.(3). The content of this additional condition would be unchanged. This would eliminate the need for both Appendix C and Section 2.I, and place all additional conditions in a common section of the FOL. The licensees proposed changes are acceptable.
2.C(4)(a), 2.C(4)(b), 2.C(4)(c), 2.C(4)(d), and 2.C(4)(e)
The licensee proposes to delete FOL Section 2.C(4). The original license condition contained five separate requirements within 2.C.(4). License Amendment No. 90, dated May 26, 1988, deleted FOL Sections 2.C(4)(a),
2.C(4)(b), 2.C(4)(d), and 2.C(4)(e). Removal of Sections 2.C(4)(a), 2.C(4)(b),
2.C(4)(d), and 2.C(4)(e) is considered an editorial change. 2.C.(4)(c) involves the testing of the wide range and narrow range resistance temperature detectors (RTDs) on the Unit 2 reactor coolant system until the RTDs are replaced with fully qualified components. These RTDs were replaced with qualified components in 1984. NRC Inspection Report 50-339-84-33, item 9 identifies this license condition as Closed. On this basis, since the condition of the component replacement has been met, closure was documented, and the license condition no longer applies, FOL 2.C.(4)(c) may be deleted. The licensees proposed changes are acceptable.
2.C.(5)
The licensee has proposed deleting the current section, as discussed in paragraph 1 below, and replacing it with a new license condition discussed in paragraph 2 below.
- 1. The current license condition involves the development of a surveillance program for the fiberglass spray pond piping and supports prior to the facility operating above 25% power. NRC Inspection Report No. 50-339-85-12 (Item 7) acknowledged the licensee has increased the inspection frequency of the spray array, and increased the surveillance of the arrays to identify spray risers needing repair. In addition, NRC Inspection Report No. 50-339-85-12 (Item 7) indicates the licensee has complied with FOL 2.C.(5) and Regulatory Guide 1.72.
Thus, this license condition has been met and the licensees proposal is acceptable.
- 2. In FOL Section 2.C.(2), the licensee has proposed deleting the reference to Appendix B, Environmental Technical Specifications (ETS). License Amendment No. 31, dated May 5, 1983, was associated with the Radiological Effluent Technical Specifications. This amendment removed Part I of the ETS and renamed it Part II of the Environmental Protection Plan (EPP). As an administrative correction, Section 2.C.(2) has been split by this proposed change such that 2.C.(2) only refers to the Technical Specifications of Appendix A.
2.C(5) is identical to Section 2.C.(2) except for referencing the EPP rather than the TS as the subject of the section. The amendment number stated in the proposed new paragraph is the latest amendment which revised the EPP.
The New FOL 2.C.(5) is to read as follows:
(5) Environmental Protection Plan The Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 178, is hereby incorporated in the license. The licensee shall operate the facility in accordance with the Environmental Protection Plan.
The licensees proposed changes are acceptable.
2.C.(6)
The licensee has proposed deleting this section of the FOL. This license condition involves the performance of secondary flow stability tests that were to be completed prior to the facility operating above 90% power. NRC Inspection Report No. 50-339-80-31 (Item 9) notes that this test was successfully performed on September 9, 1980, and identifies this license condition as closed. A subsequent letter from the NRC dated October 17, 1980, notified the licensee they had met the requirements for this license condition. The licensees proposed change is acceptable.
2.C.(7)
The licensee has proposed deleting this section of the FOL. This license condition involves transformer tap setting measurements and demonstrating that they were in agreement with the analysis prior to the facility operating above 90% power. NRC Inspection Report No. 50-339-80-33 (Item 5a) noted that this test was successfully performed on September 27, 1980, and identifies this license condition as closed as of October 3, 1980. A subsequent letter from the NRC dated October 17, 1980, notified the licensee they had met the requirements for this particular license condition. The licensees proposed change is acceptable.
2.C.(8)
The licensee has proposed deleting this section of the FOL. This license condition involves the visual inspection of feedwater hydraulic snubbers prior to the facility operating above 90% power. NRC Inspection Report No.
50-339-80-33 (Item 5b) noted that this license condition was closed as of October 10, 1980. A subsequent letter from the NRC dated October 17, 1980, notified the licensee they had met the requirements for this particular license condition. The licensees proposed change is acceptable.
2.C.(9)
The licensee has proposed deleting this section of the FOL. This is a licensing condition authorizing the use of a radioactive tracer element, Sodium-24. There are no planned moisture carryover tests for Unit 2 steam generators. In the event that such a test is deemed necessary in the future, a non-radioactive chemical tracer would be used. The acceptability of the chemical tracer techniques has been demonstrated at North Anna and therefore this specific authorization for use of Sodium-24 is no longer needed. The licensees proposed change is acceptable.
2.C.(10)
The licensee has proposed deleting this section of the FOL. This license condition involves the installation of a backup overcurrent protection system for containment electrical penetrations. NRC Inspection Report No. 50-339-83-11 (Item 9b) indicates this license condition has been satisfactorily completed. The licensees proposed change is acceptable.
2.C.(11)
The licensee has proposed deleting this section of the FOL. This license condition involves the implementation of fire protection modifications identified in the staffs Safety Evaluation Report Fire Protection Program for North Anna Power Station, Units 1 and 2, dated February 1979. These modifications were to be completed by November 1, 1980, except for the alternative shutdown system, which was to be modified by April 1, 1981. The staff conducted an inspection of the licensees Fire Protection Program at North Anna Power Station, along with their compliance with 10 CFR Part 50, Appendix R. NRC Inspection Report No. 50-339-85-24 identified one unresolved item related to the February 1979 Safety Evaluation Report that was later resolved in NRC Inspection Report No. 50-339-87-37. License Amendment No, 123 dated September 13, 1990, implemented a new fire protection license condition 2.C.(23), which required the facility to implement and maintain in effect all provisions of the approved fire protection program as described in the UFSAR and Safety Evaluation Report dated February 1979. This license amendment effectively superseded FOL Section 2.C.(11). On this basis, the requirements for Section 2.C.(11) have been completed and closure has been documented by NRC Inspection Report No. 50-339-87-37. The licensees proposed change is acceptable.
2.C.(12)(a)
The licensee has proposed deleting this section. The modifications identified in this segment of the license condition were to be completed prior to startup following a November 1, 1980, outage for fire protection modifications. NRC Inspection Report No. 50-339-80-36 (Item 6) verified the completion of these modifications. The licensees proposed change is acceptable.
2.C.(12)(b)
The licensee has proposed deleting this section. The modifications identified in this segment of the license condition were to be completed within 6 months of the issuance of the FOL. NRC Inspection Report No. 50-339-84-06 (Item 10b) verified completion of these modifications and closed this item. The licensees proposed change is acceptable.
2.C.(12)(c)
The licensee has proposed deleting this section. The modifications identified in this segment of the license condition were to be completed prior to restart following the first refueling outage. NRC Inspection Report No. 50-339-82-14 (Item 8a) indicated this design change was completed. The licensees proposed change is acceptable.
2.C.(13)
The licensee has proposed deleting this section. This license condition involves the completion and submittal of a piping re-analysis, which included seismic amplified response spectra, no later than May 22, 1981. A letter from the NRC dated May 29, 1981, acknowledged receipt of the re-analysis and closed this license condition. The licensees proposed change is acceptable.
2.C.(14)
The licensee has proposed deleting this section of the FOL. This license condition requires the submittal of plant information no later than 6 months from the issuance of the FOL to confirm the validity of the main steam line and feedwater break analysis. A letter from the NRC dated March 6, 1981, acknowledged receipt of this information and completion of this license condition.
Another letter from the NRC dated October 4, 1982, stated that this matter was closed and no further action was required from the licensee. The licensees proposed change is acceptable.
2.C.(15)(a)
The licensee has proposed deleting this section of the FOL. This license condition involves the submittal of an inspection program for control rod guide thimble tube wall wear. A letter from the NRC dated April 21, 1982, acknowledged receipt of this information and completion of the license condition The licensees proposed change is acceptable.
2.C.(15)(b)
The licensee has proposed deleting this section of the FOL. This license condition required the installation of inspection ports on the steam generators.
NRC Inspection Report No. 50-339-82-14 (Item 8.b) verified completion of the modifications. The licensees proposed change is acceptable.
2.C.(15)(c)
This section was deleted by License Amendment No. 127 dated February 20, 1991. The licensees proposal to delete this section is acceptable.
2.C.(15)(d)
The licensee has proposed deleting this section of the FOL. This license condition involves the installation of leak test connections in the residual heat removal system isolation valves. NRC Inspection Report No. 50-339-82-14 (Item 8d) verified completion and acceptability of the modifications. The licensees proposed change is acceptable.
2.C.(15)(e)
The licensee has proposed deleting this section of the FOL. This license condition requires the licensee to test the backup depressurization capability of the power-operated relief valves. NRC Inspection Report No. 50-339-82-13 (Item 10.b.(10)) determined that the license condition was met. The licensees proposed change is acceptable.
2.C.(15)(f)
The licensee has proposed deleting this section of the FOL. This license condition required the licensee to provide the results of a study involving boron mixing and cooldown performed under natural circulation conditions. A letter from the NRC dated April 22, 1982, acknowledged receipt of the test data and closed this license condition. The licensees proposed change is acceptable.
2.C.(15)(g)
The licensee has proposed deleting this section of the FOL. This license condition required the retesting of all engineered safety features reset control actions to verify proper reset action. NRC Inspection Report No. 50-339-82-14 (Item 8e) verified completion and acceptability of the retest. The licensees proposed change is acceptable.
2.C.(15)(h)(1) The licensee has proposed deleting this section of the FOL. This license condition involves the completion of a formal training program for maintenance, supervisors, and quality control personnel who are responsible for the operation of the emergency diesel generators. NRC Inspection Report No. 50-339-84-33 (Item 9) verified completion of this training. The licensees proposed change is acceptable.
2.C.(15)(h)(2) The licensee has proposed deleting this section of the FOL. This license condition requires that the diesel generator lube oil system be modified to provide continuous lubrication of the lower portions of the engine, and provide for partial filling of the upper lube oil supply header and lube oil booster/accumulator system. NRC Inspection Report No. 50-339-83-11 (Item 9c) indicated the design change has been completed and the license condition has been satisfactorily completed. The licensees proposed change is acceptable.
2.C.(15)(h)(3) The licensee has proposed deleting this section of the FOL. This license condition required the modification of the diesel generator operating procedures.
NRC Inspection Report No. 50-339-80-31 (Item 11) notes that the licensee met the license requirements and the license condition was closed. The licensees proposed change is acceptable.
2.C.(15)(h)(4) The licensee has proposed deleting this section of the FOL. This license condition requires the diesel generator fuel oil storage and transfer system be modified to include a separate high level alarm for each day tank and install independent pressure switches for each pump. The licensee was also required to submit TS changes to verify proper operation of these modifications. A letter from the NRC dated June 15, 1983, indicated the modifications were completed, and that the definition of Operable - Operability in Section 1.0 of the TS provided the method of verifying proper operation of these systems. Thus, a TS change was not required. NRC Inspection Report No. 50-339-84-30 (Item 7) verified completion of this item. The licensees proposed change is acceptable.
2.C.(15)(h)(5) The licensee has proposed deleting this section of the FOL. This license condition involves the installation of an emergency fill line to the underground 7-day fuel oil storage tank. NRC Inspection Report No. 50-339-82-14 (Item 8f) verified completion of this item. The licensees proposed change is acceptable.
2.C.(15)(h)(6) The licensee has proposed deleting this section of the FOL. This license condition required the licensee to either floor mount the control cabinet for the diesels or provide vibration tests that verify their operation during prolonged diesel operation. NRC Inspection Report No. 50-339-82-14 (Item 8g) verified installation of the floor mounts. The licensees proposed change is acceptable.
2.C.(16)
The licensee has proposed deleting this section of the FOL. This license condition involves the submittal of a schedule for compliance with Regulatory Guide 1.97. A letter from the NRC dated March 31, 1981 found the licensees March 20, 1981 submittal adequate for meeting the requirements set forth in this license condition. The licensees proposed change is acceptable.
2.C.(17)
The licensee has proposed deleting this section of the FOL. This license condition involves the inspection and submittal of the inspection results to the staff regarding the low pressure turbines. These inspections were to be conducted prior to the restart of the plant following the second refueling outage.
NRC Inspection Report No. 50-339-83-11 (Item 9e) confirmed that the inspection was completed and that this license condition was satisfied. An NRC letter dated June 20, 1983, also closed this license condition. The licensees proposed change is acceptable.
2.C.(18)
The licensee has proposed deleting this section of the FOL. This license condition required the licensee to demonstrate that their examination techniques provided a reliable means of detection and evaluation of reactor vessel clad cracking. NRC Inspection Report No. 50-339-85-26 (Item 16) documents the closure of this item. The licensees proposed change is acceptable.
2.C.(19)
The licensee has proposed deleting this section of the FOL. This license condition required the licensee to submit the results of radiation thermal testing performed on the encapsulated saddle material used for shielding. This test was to be conducted within 5 years of the issuance of the FOL, and the test results and evaluation to be submitted to the NRC within 6 months of the testing. This testing and subsequent evaluation were submitted in a letter to the NRC dated August 13, 1981. This letter completed the requirements of this license condition. The licensees proposed change is acceptable.
2.C.(20)(a)
The licensee has proposed deleting this section of the FOL. This license condition involves the evaluation of benefits with regards to the installation of data recording and logging equipment in the control room, within the schedule of NUREG-0737, Item 1.D.1. The NRC provided a letter dated February 28, 1990, which closed out the control room design issue of NUREG-0737, Supplement 1.
The licensees proposed change is acceptable.
2.C.(20)(b)
The licensee has proposed deleting this section of the FOL. This license condition required the evaluation of low power physics tests results involving boron mixing and cooldown testing for incorporation into the simulator located at Surry Power Station. This was to be completed within 1 year from the date this FOL was issued. A NRC letter dated May 4, 1982, stated that the licensee had met the requirements of this license condition. The licensees proposed change is acceptable.
2.C.(20)(c)
The licensee has proposed deleting this section of the FOL. This particular condition involves the endurance test of the steam-driven auxiliary feedwater pump. A letter from the NRC dated December 9, 1980, acknowledged completion of the test and license condition requirements. The licensees proposed change is acceptable.
2.C.(20)(d)
The licensee has proposed deleting this section of the FOL. This license condition required the licensee to maintain an emergency plan that met 10 CFR Part 50, Appendix E and NUREG-0654. VEPCO was also required to provide an emergency operations facility as a base for coordination of activities, and report to the NRC the status of action items related to emergency preparedness identified by Federal Emergency Management Agency or the NRC.
10 CFR 50.54(q) requires a licensee to maintain emergency plans that meet the standards of 10 CFR 50.47(b) and the requirements of 10 CFR Part 50, Appendix E. 10 CFR 50.47(b) contains the minimum requirements for an emergency plan, which includes support facilities. Therefore, the requirements set forth in 10 CFR Part 50 supersedes the need for this license condition, which has become obsolete. The licensees proposed change is acceptable.
2.C.(21)(a)
The licensee has proposed deleting this section of the FOL. This particular condition involves the training requirements for the Shift Technical Advisor. NRC Inspection Report No. 50-339-84-33 (Item 9) closed this license condition. The licensees proposed change is acceptable.
2.C.(21)(b)
The licensee has proposed deleting this section of the FOL. This particular condition involves the administration of training programs for licensed operators.
NRC Inspection Report No. 50-339-84-33 (Item 9) closed this license condition.
The licensees proposed change is acceptable.
2.C.(21)(c)
The licensee has proposed deleting this section of the FOL. This license condition involves the installation, procedural guidelines, and analytical basis for the reactor vent system. NRC Inspection Report No. 50-339-84-33 (Item 9) confirmed that the installation and testing for the vent system had been completed, but had left this item open. NRC Inspection Report No. 50-339-85-12 (Item 12a.) closed this license condition. The licensees proposed change is acceptable.
2.C.(21)(d)
The licensee has proposed deleting this section of the FOL. This particular condition involves plant shielding evaluations and necessary modifications to assure access to vital areas in post-accident conditions. NRC Inspection Report No. 50-339-84-33 (Item 9) closed this license condition. The licensees proposed change is acceptable.
2.C.(21)(e)
This section of the FOL was deleted by License Amendment No. 210 dated December 19, 2001.
2.C.(21)(f)
The licensee has proposed deleting this section of the FOL. This license condition involves the qualification of the pressurizer safety valves and power-operated relief valves (PORVs). NRC Inspection Report No. 50-339-84-33 (Item
- 9) indicated that testing was completed; however, the staff had additional questions that needed to be resolved. A letter from the staff dated March 21, 1989, evaluated the relief and safety valves in accordance with NUREG-0737, Item II.D.1. The staffs evaluation indicated that the requirements of NUREG-0737, Item II.D.1 had been partially met. The licensee had demonstrated by testing and analysis for all items reviewed, except for the PORV control circuitry, that the reactor coolant system (RCS) boundary would have a low probability of abnormal leakage and that the design conditions of the RCS boundary and its associated components would not be exceeded during relief and safety valve events. This same letter stated the licensees submittals had not demonstrated the PORV control circuits met the qualification requirements of NUREG-0737, Item II.D.1, since neither the PORV control circuits or the PORV block valves were environmentally qualified. The licensee responded with a letter to the staff on October 15, 1990, where they indicated that in accordance with Generic Letter (GL) 90-06, the PORV valves did not need to be environmentally qualified components as a maintenance and testing program was to be implemented.
License Amendment 170 dated October 5, 1994, incorporated this maintenance and program as required by GL 90-06. The licensee has completed the testing requirements set forth in this license condition; therefore, their proposed change is acceptable.
2.C.(21)(g)
The licensee has proposed deleting this section of the FOL. This particular condition involves the safety-grade indication for feedwater flow. NRC Inspection Report No. 50-339-84-33 (Item 9) indicated this item was evaluated and accepted by the staff. NRC Inspection Report No. 50-339-84-33 further stated that this license condition was closed. The licensees proposed change is acceptable.
2.C.(21)(h)
The licensee has proposed deleting this section of the FOL. This particular condition involves the dedicated containment penetration for combustible gas (hydrogen) control in the post-accident condition. NRC Inspection Report No.
50-339-82-04 (Item 8) concluded that the installed system met the requirements of Item II.E.4.1 and closed this item. NRC Inspection Report No. 50-339-84-33 (Item 9) closed this license condition. The licensees proposed change is acceptable.
2.C.(21)(i)(i)
The licensee has proposed deleting this section of the FOL. This license condition involves the installation and operation of instrumentation used to monitor containment pressure. NRC Inspection Report No. 50-339-84-33 (Item 9) confirmed this license condition was inspected and closed in NRC Inspection Report No. 50-339-84-06. The licensees proposed change is acceptable.
2.C.(21)(i)(ii)
The licensee has proposed deleting this section of the FOL. This license condition involves the installation and operation of instrumentation used to monitor containment water level. NRC Inspection Report No. 50-339-84-33 (Item 9) confirmed this license condition was inspected and closed in NRC Inspection Report No. 50-339-84-06. The licensees proposed change is acceptable.
2.C.(21)(i)(iii) The licensee has proposed deleting this section of the FOL. This license condition involves the installation and operation of instrumentation used to monitor containment atmosphere hydrogen concentration. NRC Inspection Report No. 50-339-84-33 (Item 9) confirmed this license condition was inspected and closed in NRC Inspection Report Nos. 50-339-84-06 and 50-339-84-09. The licensees proposed change is acceptable.
2.C.(21)(i)(iv) The licensee has proposed deleting this section of the FOL. This license condition involves the installation and operation of instrumentation used to monitor containment high radiation. NRC Inspection Report No. 50-339-84-33 (Item 9) confirmed this license condition was inspected and closed in NRC Inspection Report No. 50-339-84-07. The licensees proposed change is acceptable.
2.C.(21)(i)(v)
The licensee has proposed deleting this section of the FOL. This license condition involves the installation and operation of instrumentation used to monitor noble gas effluent from potential release points and provide for continuous sampling of radioiodine and particulates. This license condition was inspected and closed in NRC Inspection Report No. 50-339-87-08 (Item 6). The licensees proposed change is acceptable.
Therefore, based upon the staffs analysis of FOL Sections 2.C.(21)(i)(i) through 2.C.(21)(i)(v),
FOL Section 2.C.(21)(i) may be deleted.
2.C.(21)(j)
The licensee has proposed deleting this section of the FOL. This particular condition involves the installation and demonstration of additional indications of inadequate core cooling instrumentation. NRC Inspection Report No.
50-339-84-33 (Item 9) closed this license condition and noted that this item was inspected and closed in NRC Inspection Report No. 50-339-81-03. The licensees proposed change is acceptable.
2.C.(22)
The licensee proposed to correct the spelling of license and add a comma.
This Section is to be renumbered as new FOL Section 2.C(4). These are editorial changes, thus the licensees proposal is acceptable.
2.C.(23)
The licensee has proposed that the references to the FSAR be changed to UFSAR. 10 CFR 50.71(e) requires licensees to periodically update their FSAR and adopts the term updated to refer to this process. Thus, the UFSAR is understood to mean the most up-to-date version of the FSAR and no further identification is necessary. The licensees proposed change is acceptable.
The licensee has proposed relocating this section to new FOL section 2.D. No technical changes are proposed. Since the fire protection program is specifically a requirement according to 10 CFR Part 50, Appendix R, it does not fit the definition of Additional Conditions and is relocated to its own license section.
This is consistent with the treatment of the security requirements of 10 CFR Part 73 in FOL 2.E, Physical Security. The licensees proposed change is acceptable.
2.C.(24)
The licensee has proposed deleting this section of the FOL. This license condition was added by License Amendment No. 185 dated May 9, 1997, to allow the licensee to use up to four demonstration fuel assemblies containing advanced zirconium-based alloys. Since these demonstration fuel assemblies were placed in the Unit 1 reactor core, the licensee has no plans to use these assemblies for Unit 2. Therefore, this license condition is not needed. The licensees proposed change is acceptable.
2.D.
The licensee has proposed deleting this section of the FOL. This section involves an exemption to 10 CFR Part 50, Appendix J, regarding leak testing of the containment personnel airlock (PAL). This exemption allowed leak testing of the PAL within 3 days of opening the PAL. This license condition along with a footnote to TS 3.6.1.3 acknowledged this exemption. 10 CFR Part 50, Appendix J, D.2.(b)(iii) was later revised to require testing within 3 days after the PAL has been opened for Type B testing. License Amendment No. 177 dated February 9, 1996, removed the footnote to TS 3.6.1.3, but not the license condition. Since the exemption is no longer required, the license condition can be removed. The licensees proposed change is acceptable.
2.F.
The licensee proposes to delete FOL 2.F. License Amendment No. 93 dated December 5, 1988, incorporated License Condition 2.F into the North Anna, Unit 2 FOL. License Condition 2.F authorizes the modification of the design of the reactor coolant pump and steam generator supports in accordance with a submittal dated November 6, 1986, as supplemented by letters dated February 24 and March 12, 1987, and March 8 and June 10, 1988. The change in design was conducted to take advantage of the approved advanced fracture mechanics methods associated with Leak-Before-Break Technology permitted by the General Design Criteria 4 of Appendix A to 10 CFR Part 50. The licensees submittal dated January 9, 2001, stated that the modifications were completed during the Spring 1989 refueling outage. Since the modifications have been completed, FOL 2.F is no longer needed. The licensees proposal to delete this section is acceptable.
2.G.
The licensee proposes to relocate this section to new section 2.C(3)(a).
Relocation of this license condition has no impact upon the technical aspects of the item being relocated. The licensees proposed change is acceptable.
2.H.
The licensee proposes to modify this license condition to read as follows:
VEPCO shall report any violations of this requirement within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate, no later than the first working day following the violation, with a written followup report within 14 days.
In addition, the licensee proposes to relocate this modified section to new section 2.C(3)(a). Relocation of this modified license condition has no impact on the technical aspects of the item being relocated.
References to license conditions 2.C(3) through 2.C(21), E, F, and G are to be deleted. As proposed in this change request License Conditions 2.C(3) through 2.C.(21) are to be removed since they have been completed and are now obsolete.
The original section 2.E required the licensee to maintain in effect and implement all provisions of the NRC approved Safeguards Contingency Plan identified as Chapter 8 in the North Anna Power Station, Units 1 and 2, Security Plan. The original intent of section 2.H was to require the reporting of violations to various license conditions including 2.E. The current license condition 2.E was implemented by License Amendment No. 87 dated May 9, 1988, and refers to 10 CFR 73.55. 10 CFR 73.71 and 10 CFR Part 73, Appendix G provide the reporting requirements for safeguards events. Thus, the security reporting requirements associated with license condition 2.H have been superseded by 10 CFR 73.71 and 10 CFR Appendix G.
The original License Condition 2.F involved environmental issues that have since been removed. Subsequent changes to this license condition contained no discussion regarding the applicability of the reporting requirements stated in License Condition 2.H.
License Condition 2.G. is being relocated to new FOL section 2.C(3)(a) and will be combined with the modified License Condition 2.H that is also being relocated to 2.C(3)(a).
The licensees proposed change is acceptable.
2.I.
The licensee proposes to delete this section. The licensee has proposed to relocate Appendix C text to FOL 2.C.(3)(b). Relocation of license conditions within the FOL has no impact on the technical aspects of the item being removed.
Currently, 2.I references FOL Appendix C. In an effort to construct a clean, concise FOL document, the proposed change would move the single Appendix C requirement to within the existing Additional Conditions section of the FOL. This would support the removal of FOL Section 2.I. The content and applicability of this additional condition would be unchanged. The licensees proposed changes are acceptable.
2.J.
The licensee proposes to renumber this section as new FOL section 2.F. This is an editorial change and is acceptable.
Listing of Attachments on Page 14 of FOL The licensee proposes to replace the listing of attachments with the following list:
- 1. Appendix A, Technical Specifications
- 2. Appendix B, Environmental Protection Plan This is an editorial change. The licensees proposal is acceptable.
Appendix C The licensee proposes to relocate Appendix C text to new section 2.C.(3)(b) and delete the FOL Appendix C cover page. Relocation of license conditions within the FOL has no impact on the technical aspects of the item being removed.
Appendix C was added by License Amendment No. 195 dated August 26, 1998.
In an effort to construct a clean, concise FOL document, the proposed change would move the single Appendix C requirement to within the existing Additional Conditions section of the FOL. The content and applicability of this additional condition would be unchanged. This would eliminate the need for Appendix C and place all additional conditions in a common section of the FOL. The licensees proposal is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact has been published in the Federal Register on February 13, 2002 (67 FR 6765). Accordingly, the Commission has determined that the issuance of these amendments will not result in any environmental impacts other than those evaluated in the Final Environmental Statement.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: K. Desai S. Rhow A. Lee S. Monarque Date: March 19, 2002
Mr. David A. Christian North Anna Power Station Virginia Electric and Power Company Units 1 and 2 cc:
Mr. C. Lee Lintecum Mr. David A. Heacock County Administrator Site Vice President Louisa County North Anna Power Station P.O. Box 160 P.O. Box 402 Louisa, Virginia 23093 Mineral, Virginia 23117-0402 Ms. Lillian M. Cuoco, Esq.
Senior Nuclear Counsel Mr. Richard H. Blount, II Dominion Nuclear Connecticut, Inc.
Site Vice President Millstone Power Station Surry Power Station Building 475, 5th Floor Virginia Electric and Power Company Rope Ferry Road 5570 Hog Island Road Rt. 156 Surry, Virginia 23883-0315 Waterford, Connecticut 06385 Dr. W. T. Lough Robert B. Strobe, M.D., M.P.H.
Virginia State Corporation State Health Commissioner Commission Office of the Commissioner Division of Energy Regulation Virginia Department of Health P.O. Box 1197 P. O. Box 2448 Richmond, Virginia 23209 Richmond, Virginia 23218 Old Dominion Electric Cooperative Mr. William R. Matthews 4201 Dominion Blvd.
Vice President - Nuclear Operations Glen Allen, Virginia 23060 Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Mr. Stephen P. Sarver, Director Glen Allen, Virginia 23060-6711 Nuclear Licensing & Operations Support Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117