ML20036A830
| ML20036A830 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/06/1993 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20036A829 | List: |
| References | |
| 2130, NUDOCS 9305170060 | |
| Download: ML20036A830 (6) | |
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Docket Number 50-346 License Number NPF-3 Serial-Number 2130 l
Enclosure l
Page 1 I
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l APPLICATION FOR AMENDMENT
].i TO FACILITY OPERATING LICENSE NUMBER NPF-3 l
I DAVIS-BESSE NUCLEAR POVER STATION i
UNIT NUMBER 1 j
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Attached are requested changes to the Davis-Besse Nuclear Pover j
Station, Unit Number 1, Facility Operating License Number NPF-3.
Also l
included is the-Safety Assessment and Significant Hazards
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Consideration.
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The proposed changes submitted under cover letter Serial Number i
j concern:
Appendix A, Technical Specification 3/4.4.5, Reactor Coolant i
System - Steam Generators Appendix A, Technical Specifications 1.32, 3.3.3.9, 3.11.1, 6.5.1.6, 6.9.1.11 and 6.15'(Semiannual Radioactive Effluent Release Report) p j
,. k/\\/k By:
D. C. Shel' ton, V:Me Presidenf - Nuclear
- l Svorn and subscribed before me this 6th day of May,1993.
J k/A/Jhb df Notary Pv611c, State of Ohio
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I 93o517o060 930506 PDR ADOCK 05000346 l
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Docket Number 50-346
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License Number NPF-3 Serial Number 2130 Enclosure j
Page 2 The following information is provided to support issuance of the requested changes to the Davis-Besse Nuclear Power Station, L' nit Number 1, Operating License Number NPF-3, Appendix A Technical Specifications (TS) 3/4.4.5, Reactor Coolant System - Steam Generators l
and its associated Bases regarding reporting tube inspection category
-i C-3 results, and TS 1.32, 3.3.3.9, 3.11.1, 6.5.1.6, 6.9.1.11 and 6.15 i
regarding the Semiannual Radioactive Effluent Release Report.
l A.
Time Required to Implement: This change is to be implemented within 90 days after the NRC issuance of the license amendment.
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B.
Reason for Change (License Amendment Request Number 92-0012):
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The proposed changes vould clarify the reporting requirements contained in TS 4.4.5.5c,'TS Table 4.4-2, and associated Bases l
3/4.4.5 regarding notification to the NRC of Steam Generator tube j
inspection Category C-3 results. This vould also make the i
'i reporting requirements consistent with the New Standard Technical Specifications, NUREG-1430, Revision 0, TS 5.9.2.
The proposed changes to TS 1.32, 3.3.3.9, 3.11.1, 6.5.1.6, 6.9.1.11 and 6.15 vould revise the frequency requirement for the submission to the NRC of the Radioactive Effluent Report from semiannually to j
annually. This frequency revision is consistent with the recent j
revision to 10 CFR 50.36a, Technical Specifications on Effluents j
l from Nuclear Power Reactors, C.
Safety Assessment and Significant Hazards Consideration:
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Docket h mber 50-346 s
License Number NPF-3 Serial Number 2130 Attachment Page l-l SAFETY ASSESSMENT AND SIGNIFICANT HAZARDS CONSIDERATION FOR j
LICENSE AMENDMENT REQUEST NUMBER 92-0012 TITLE.
Revision of Technical Specification (TS) 6.9.1.11 and other Related l
TSs to Change the Submittal Frequency of the Radioactive Effluent l
Release Report from Semiannual to Annual; and Revision of Reporting i
Requirements Referenced in TS 3/4.4.5, Steam Generators.
DESCRIPTION:
The purpose of this license amendment request is to propose modification of the Davis-Besse Nuclear Power Station (DBNPS) Operating l'
License NPF-3, Appendix A, Technical Specifications regarding:
1.
Changing the frequency requirements in the TS 6.9.1.11 and related TSs from semiannually to annually for submission to the NRC of the Radioactive Effluent Release Report, and 2.
Clarifying the reporting requirements contained in TS 4.4.5.Sc, TS l
Table 4.4-2, and associated TS Bases 3/4.4.5 regarding notification j
to the NRC of steam generator tube inspection Category C-3 results.
i An editorial correction is also proposed to TS 4.4.5.2a.3 to correct a minor error.
Federal Register, Volume 57, Number 169, dated August 31, 1992, entitled " Reducing the Regulatory Burden on Nuclear Licensees" announced the revision of the NRC's regulations in 10 CFR 50.36a~,
" Technical Specifications on Effluents from Nuclear Power Reactors",
regarding the frequency requirements for submittal of Radiological Effluent Release Reports. This final rule, effective October 1, 1992, revised the regulations for the submission of reports concerning the l
quantity of principal nuclides released to unrestricted areas in liquid and gaseous effluents from a semiannual to an annual frequency.'
In accordance with the new rule, this license amendment request i
proposes administrative changes to Technical Specifications 1.32 (Definitions - Offsite Dose Calculation Manual (ODCM)), 3.3.3.9 (Instrumentation - Vaste Gas System Oxygen Monitor), 3.11.1 l
(Radioactive Effluents - Liquid Holdup Tanks), 6.5.1.6s i
(Responsibilities (Station Review Board)), 6.9.1.11 (Semiannual Effluent Release Report), and 6.15 (cf.fsite Dose Calculation Manual
.j (ODCM)).
In addition, this license amendment request proposes administrative changes to Technical Specification 4.4.5.5c, Reports, and Table 4.4-2 (Steam Generator Tube Inspection), and associated TS Bases 3/4.4.5, Steam Generators, which currently require notification to the NRC pursuant to'TS 6.9.1, Routine Reports, of steam generator tube inspection results which fall into Category C-3.
Category C-3 results
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Docket-Number 50-346' License Number NPF-3 Serial Number 2130 i
i Attachment Page 2 can exist when more than ten percent of the total tubes inspected are j
degraded tubes or more than one percent of the inspected tubes are i
defective.
" Degraded tubes" and " defect" are defined in TS 4.4.5.4.
The proposed changes to TS 4.4.5.5c, Table 4.4-2, and associated TS j
Bases 3/4.4.5, vould clarify the required reporting requirements regarding notificatien to the Commission of the results of steam generator tube inspections which fall into Category C-3 prior to l
I resumption of plant operation.
An additional administrative thange is proposed to delete Note (2) of Table 4.4-2.
Note (2) summarizes information already found in the table and, therefore, is not required.
An editorial correction is also proposed to T5 4.4.5.2a.3 to correctly reference the appropriate TS definition of tube inspection in TS 4.4.5.4a.9 (not TS 4.4.5.4a.8).
SYSTEMS, COMPONENTS, AND ACTIVITIES AFFECTED:
j These proposed changes affect activities associated with the reporting
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of Category C-3 steam generator tube inspection results to the NRC, and the frequency of submitting Radiological Effluent Release Reports to l
the NRC.
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SAFETY FUNCTION OF THE AFFECTED SYSTEMS, COMPONENTS AND ACTIVITIES:
The Radiological Effluent Release Report provides the NRC with.a l
summary of the quantity of principal nuclides released to unrestricted i
t areas in liquid and gaseous effluents, summarizes the quantities of.
radioactivity contained in solid vaste packaged and shipped for offsite
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disposal, and estimates the maximum potential radiation doses to the public resulting from effluent releases.
The function of the reporting requirements for steam generator tube inspections results which fall into Category C-3 is to require I
notification to the NRC prior to the resumption of power operation.
l Such results will be considered by ;he NRC on a case-by-case basis and j
may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, or revision of the Technical Specifications, if necessary.
i EFFECTS ON SAFETY:
i The Semiannual Radioactive Effluent Release Report under TS 6.9.1.11 is currently submitted within 60 days after January 1 and July 1 of each year and covers the operation period for the previous six months. The proposed revision vould delete the word " semiannual" and the words "during the previous six months of operation shall be submitted within 60 days af ter January and July 1 of each year."
The proposed wording would require submittal of the Radioactive Effluent Release Report in accordance with revised 10CFR50.36a. This change is consistent with the intent of the Federal Register notice, entitled " Reducing the Regulatory Burden on Nuclear Licensee", Volume 57, Number 169, dated
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t Docket Number 50-346 License Number NPF-3 Serial' Number 2130 l
Attachment Page 3 August 31, 1992 which identified that the NRC resident inspector l
program along with regional regulatory programs provide _ timely reviev of plant operations and that the changes vill not impair the NRC's
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ability to review the information (page 39355).
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The proposed wording is consistent with the wording of the new Standard i
l Technical Specifications for Babcock and Vilcox Type Nuclear Steam.
Supply Systems, NUREG-1430, Revision 0, dated September 28, 1992, TS i
5.9.1.4, Radioactive Effluent Release Report. A particular date is no longer speci'ied because it "... gives the licensee maximum j
flexibility for scheduling submission of radiological effluent reports l
I vith the only restriction that the interval between reports must not exceed 12 months" (Federal Register Volume 57, Mumber 169, August 31, i
1992, page 39354).
The NRC concluded that this change in reporting from semiannually to annually does not reduce the protection for public health and safety.
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The reporting of defective steam generator tubes which fall into I
Category C-3 under TS 4.4.5.5c and Table 4.4-2 is currently required by i
TS to be performed pursuant to TS 6.9.1.
However, the reporting
_j requirements which previously existed in TS 6.9.1 vere deleted with License Amendment Number 93.
License Amendment Number 93, in turn, vas r
proposed and approved based on the NRC's recommendations in Generic i'
Letter 83-43 (Reporting Requirements of 10CFR Part 50, Section 50.72 and 50.73, and Standard Technical Specifications) dated December 19, 1983. Toledo Edison's license amendment request and License Amendment Number 93 did not identify that.a change to TS 4.4.5.Sc and Table 4.4-2 1
vas necessary. This oversight was later identified by Toledo Edison's self-initiated Technical Specification Verification Program. The i
proposed revision vould require notification to the NRC of the results I
of steam generator tube inspections which fall into Category C-3, prior to resumption of plant operation.
The proposed changes to the reporting requirements of defective steam l
generator tubes which fall into Category C-3, and the submittal j
frequency of the Radiological Ef fluent Release Report are l
i administrative changes, and vill have no adverse effect on safety. The proposed deletion of Note (2) to TS Table 4.4-2 is an administrative change and vill have no adverse effect on safety. The proposed changes 4
to TS 4.4.5.2a.3 to reference the steam generator tube inspection j
definition is an editorial correction, and vill have no adverse effect i
1 on safety.
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SIGNIFICANT HAZARDS CONSIDERATION:
The Nuclear Regulatory Commission has provided standards in 10 CFR j
50.92(c) for determining whether a significant hazard exists due to a I
proposed amendment to an Operating License for a facility. A proposed amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed changes vould: (1) Not involve a significant increase in the probability or consequences of an accident previously evaluated; (2) Not create the possibility of a new or different kind of accident from any accident previously evaluated;
Docket Number 50-346 1
License Number NPF-3 Serial Number 2130 Attachment Page 4 or (3) Not involve a significant reduction in a margin of safety.
Toledo E6. son has revieved the proposed changes and determined that a j
significant hazards consideration does not exist because operation of the Davis-Besse Nuclear Power Station Unit Number 1, in accordance with i
these changes vould:
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Not involve a significant increase in the probability of an accident previously evaluated because no initiators or assumptions for a previously evaluated accident are affected by the proposed administrative reporting requirement changes to TS 4.4.5.5c, Table 4.4-2, 1.32, 3.3.3.9, 3.11.1, 6.5.1.6s, 6.9.1.11 and 6.15, and Bases 3/4.4.5, or by the proposed editorial correction to l
TS 4.4.5.2a.3.
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Not involve a significant increase in the consequences of an accident previously evaluated because no equipment, accident conditions, or assumptions which could lead to an increase in
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radiological consequences are affected by these proposed administrative reporting requirement changes or editorial correction.
2a.
Not create the possibility of a new kind of accident from any l
accident previously evaluated because no new accident initiators are being introduced, no new hardware changes are being made, no i
new testing is being instituted and no new operatir.g manipulations j
are being created by these proposed administrative reporting 1
requirement changes or editorial correction.
2b. Not create the possibility of a different kind of accident from any accident previously evaluated because no different accident j
initiators are being introduced, no changes in hardware are being 1
made, no different testing is being instituted, and no different-plant manipulations are being created by these proposed administrative reporting requirement changes or editorial l
correction.
3.
Not involve a significant reduction in a margin of safety because the proposed changes do not reduce or adversely affect the capabilities of any plant structures, systems or components, and i
involve only administrative reporting requirements and an editorial correction.
CONCLUSION:
On the basis of the above, Toledo Edison has determined that the 1
License Amendment Request does not involve a significant hazards I
consideration. As the License Amendment Request concerns a proposed change to the Technical Specifications that must be reviewed by the Nuclear Regulatory Commission, this License Amendment Request does not constitute an unreviewed safety question.
1 ATTACHMENT:
Attached are the proposed mark-up changes to the Operating License.
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