ML042010134
| ML042010134 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/02/2004 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TVA-BFN-TS-449 | |
| Download: ML042010134 (13) | |
Text
Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 July 2, 2004 TVA-BFN-TS-449 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop:
OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2,
AND 3 -
TECHNICAL SPECIFICATIONS (TS)
CHANGE 449 -
APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO ELIMINATE REQUIREMENTS TO PROVIDE MONTHLY OPERATING REPORTS AND OCCUPATIONAL RADIATION EXPOSURE REPORTS Pursuant to 10 CFR 50.90, the Tennessee Valley Authority (TVA) is submitting a request for a TS change (TS-449) to licenses DPR-33, DPR-52, and DPR-68 for BFN Units 1, 2, and 3, respectively.
The proposed amendment would delete the TS requirements to submit monthly operating reports and occupational radiation exposure reports.
The change is consistent with NRC-approved Revision 1 to industry/Technical Specification Task Force (TSTF)
Standard Technical Specification Change Traveler, TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report." The availability of this TS improvement was announced in the Federal Register on June 23, 2004, as part of the Consolidated Line Item Improvement Process.
PRWed on cyded paW
U.S. Nuclear Regulatory Commission Page 2 July 2, 2004 provides a description of the proposed change and confirmation of applicability. provides the existing TS pages marked-up to show the proposed change.
TVA is asking that this TS change be approved by November 1, 2004, and that the implementation of the revised TS be made within 60 days of NRC approval.
TVA has determined that there are no significant hazards considerations associated with the proposed change and that the TS change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(10). Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and Enclosures to the Alabama State Department of Public Health.
There are regulatory commitments contained in Section 6.1 of.
If you have any questions about this TS change, please contact me at (256)729-2636.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on July 2, 2004.
St cerel:
Manager of Licen i dustry Affa rs
Enclosures:
- 1. Description and ssessment
_.Proical Specifications Changes (mark-up)
U.S. Nuclear Regulatory Commission Page 3 July 2, 2004 Enclosures cc: (Enclosures)
State Health Officer Alabama State Department of Public Health RSA Tower -
Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Browns Ferry Nuclear Plant (BFN)
Units 1, 2, and 3 Technical Specifications (TS) Change 449 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Description and Assessment
1.0 DESCRIPTION
The proposed license amendment deletes the requirements in TS 5.6.1 for an annual report on occupational radiation exposures and TS 5.6.4 for a monthly report of operating statistics and shutdown experience.
The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-369, "Removal of Monthly Operating Report and Occupational Radiation Exposure Report," Revision 1. The availability of this TS improvement was announced in the Federal Register on June 23, 2004, as part of the Consolidated Line Item Improvement Process (CLIIP).
2.0 DESCRIPTION
OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision 1 of TSTF-369, the proposed TS changes include:
TS 5.6.1 Occupational Radiation Exposure Report -
Deleted TS 5.6.4 Monthly Operating Reports -
Deleted
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369.
4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on June 23, 2004 (69 FR 35067) and TSTF-369.
5.0 TECHNICAL ANALYSIS
TVA has reviewed the safety evaluation (SE) published on June 23, 2004 (69 FR 35067) as part of the CLIIP Notice of Availability.
This verification included a review of the NRC staff's SE and the supporting information provided to support TSTF-369. TVA has concluded that the justifications presented in the TSTF proposal and the SE prepared by the NRC staff are applicable to BFN 1, 2, and 3, and justify this amendment for the incorporation of the changes to the BFN TS.
6.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability on June 23, 2004 (69 FR 35067) and TSTF-369.
6.1 Verification and Commitments As discussed in the model SE published in the Federal Register on June 23, 2004 (69 FR 35067) for this TS improvement, TVA is making the following regulatory commitments:
- 1. TVA is making a regulatory commitment to provide to the NRC using an industry database the operating data (for each calendar month) that is described in Generic Letter 97-02 "Revised Contents of the Monthly Operating Report,"
by the last day of the month following the end of each calendar quarter.
The regulatory commitment will be based on use of an industry database (e.g., the industry's Consolidated Data Entry (CDE) program, currently being developed and maintained by the Institute of Nuclear Power Operations).
This regulatory commitment will be implemented to prevent any gaps in the monthly operating statistics and shutdown experience provided to the NRC (i.e., data for all months will be provided using one or both systems (monthly operating reports and CDE)).
E1-2
The subject regulatory commitment will be maintained in the Updated Final Safety Analysis Report.
- 2. BFN has does not have different reactor types or both operating and shutdown reactors.
Therefore, no commitment is required.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION TVA has reviewed the proposed no significant hazards consideration determination published on June 23, 2004 (69 FR 35067) as part of the CLIIP.
TVA has concluded that the proposed determination presented in the notice is applicable to BFN and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
8.0 ENVIRONMENTAL EVALUATION TVA has reviewed the environmental evaluation included in the model SE published on June 23, 2004 (69 FR 35067) as part of the CLIIP.
TVA has concluded that the staff's findings presented in that evaluation are applicable to BFN Units 1, 2, and 3, and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT This application is being made in accordance with the CLIIP.
TVA is not proposing variations or deviations from the TS changes described in TSTF-369 or the NRC staff's model SE published on June 23, 2004 (69 FR 35067).
10.0 REFERENCES
Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specifications Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process, published June 23, 2004 (69 FR 35067).
E1-3 Browns Ferry Nuclear Plant (BFN)
Units 1, 2, and 3 Technical Specifications (TS) Change 449 Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Proposed Technical Specifications Changes (mark-up)
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 e,
Occupational Radiation Exposure Report I
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-NOTE Apngle submittal may e made for a multoe unit static ould combine se ns common to all its at the stat Ln. The su al A tabulation an annual basis the number of station, ility, and other personn (including contract
), for whom monitorin as performed, receiv g an annual deep d e equivalent > 100 mr s and the ass iated collective dee dose equivalent (repo ed in person - rem) a rding to work and' functions (e.g., rea r operations and surveillance, inservic inspection, routine m ntenance, special maintenance [des e maintenance], wa e processing, and refueling).
This tabulation s plements the requir ents of 10 CFR 20.2
. The dose assignm ts to various duty fu ions may be estimate based on pocket ioniz ion chamber, thermolminescence dosimete TLD),
electronic osimeter, or film ba e measurements. Sm exposures totaling < 0 percent of the in vidual total dose need ot be accounted for. In the aggregate, at le t 80 percent of the tot deep dose equivalent received from external so rces should be assigned to specific majorhork functions. The report covering the previous ca ndar year shall submitted by April 30 of each year.
(continued)
BFN-UNIT I 5.0-22 Amendment No. 234
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
(1) The APLHGRs for Specification 3.2.1; (2) The LHGR for Specification 3.2.3; (3) The MCPR Operating Limits for Specification 3.2.2; and (4) The RBM setpoints and applicable reactor thermal power ranges for each of the setpoints for Specification 3.3.2.1, Table 3.3.2.1-1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel," (latest approved version for BFN).
(continued)
BFN-UNIT 1 5.0-24 Amendment No. 234, 239 November 21, 2000
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Occupational Radiation Exoosure Report r r----
f-------NOTE -----,-...........--.........--...........
( e 5,e < c9 A
ngle submittal m be made for a mu le unit station.
e submittal hould combine s tions common to a units at the stati.
A tabulon on an annual ba of the number station, utility, and other pers nel (including contr ors), for whom nitoring was perfo med, re yivng an annual de dose equivalent 100 mrems and th associated collective eep dose equiva nt (reported in per n - rem) according to work nd job functions g., reactor operati s and surveillance, iJrvice inspection, utine maintenance special maintenanc describe mainten ce], waste proces g, and refueling).
This tabu tion supplements e requirements of CFR 20.2206. T e dose a ignments to van s duty functions ma e estimated base on pocket ionization cha r, thermoluminesce ce dosimeter (TL electronic dosimeter or film badge measu ments. Small ex sures totaling < 20 per nt of the individual t I dose need not accounted for. In the ag gate, at least 80 per nt of the total de dose equiy nt received fro external sources sh Id be assigned t specific majwork functions. The report covering t e previous calend r year shall be submitted by April 30 of each year.
(continued)
BFN-UNIT 2 5.0-22 Amendment No. 253
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
(1) The APLHGRs for Specification 3.2.1; (2) The LHGR for Specification 3.2.3; (3) The MCPR Operating Limits for Specification 3.2.2; and (4) The RBM setpoints and applicable reactor thermal power ranges for each of the setpoints for Specification 3.3.2.1, Table 3.3.2.1-1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-2401 1-P-A, 'General Electric Standard Application for Reactor Fuel," (latest approved version for BFN).
(continued)
BFN-UNIT 2 5.0-24 Amendment No. 2-53 266 November 21, 2000
Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.
5.6.1 Occupational Radiation Exposure Report 0 J A n,
-OT---------
I A tab ton o annual basis of t number of sta tility, and other pers nnel (i luding contractors or whom monit ing was performed,,
rec iving annual deep dos equivalent > 1 mrems and the associa d collective deep se equivalent ported in person rem) accor ng to work and jo functions (e.g. eactor operations nd surv illance, inservic nspection, rout'e maintenance, s cial maintenance [descs e maintenanc waste processin,and refueling).
This tabulation s plements the r quirements of 1 R 20.2206. The dose assignm ts to various d y functions may estimated basemen pocket ioniz on chamber, t rmoluminescen dosimeter (TLD\\
electronic dosimeter, or fil badge measure ents. Small expxtures totaling < 20 percent of t e individual totalose need not b ccounted for. In the aggregate, at least 80 perce of the total dee dose equivalent received from external sources should be assigned to ecific major work functions. The report covering the previous calend ear shall be submitted by April 30 of each year.
k (continued)
BFN-UNIT 3 5.0-22 Amendment No. 212
Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.4 Mntv hl eratina Re orts R
ne repo of opera st atistics shutdow erienc all be ubmitte n a month asis no I r than the h of eac),lTonth foi ing the cal dar month covered by e report.
V 5.6.5 CORE OPERATING LIMITS REPORT (COLR)
- a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
(1) The APLHGRs for Specification 3.2.1; (2) The LHGR for Specification 3.2.3; (3) The MCPR Operating Limits for Specification 3.2.2; and (4) The RBM setpoints and applicable reactor thermal power ranges for each of the setpoints for Specification 3.3.2.1, Table 3.3.2.1-1.
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. NEDE-2401 1-P-A, General Electric Standard Application for Reactor Fuel.
- 2. XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.
- 3. XN-NF-85-67(P)(A), Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel.
- 4. EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model.
- 5. ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs.
(continued)
BFN-UNIT 3 5.0-24 Amendment No. 242-1226, 245 December 30, 2003