ML20082J875
| ML20082J875 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/23/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082J869 | List: |
| References | |
| NUDOCS 9108290046 | |
| Download: ML20082J875 (3) | |
Text
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S NUCLEAR REGULATORY COMMISSION 3.h o,
WASHINGTON. D.C. 20t46
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 160 TO FACILITY OPERATING LICENSE NO. NPF-3 l
t TOLEDO EDISON COMPANY l
CENTER 10R SERVICE COMPANY
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AND i
THE CLEVELAND ELECTRIC IU.UMINATING COMPANY DAVIS-BESSE NUCLEAR POWER STATICN. UNIT NO. 1 l
f DOCKET NO. 50-346
1.0 INTRODUCTION
i By letter dated March 1, 1991, Toledo Ediscn (the licensee) proposed changes i
totheTechnicalSpecificationsfortheDavis-BesseNuclearPowerStation}
Unit 1 (DBNPS).
The prop N changes involve Technical Specification (TS 3/4.6.1.2, " Containment Leawage," and its bases. The. proposed changes would increase the allowed secondary containn.ent bypass leakage rate from 0.015 L t l
relocate the list of secondary containment bypass leakage paths (T$ o 0.03 L Table $.,6-1) from the TS to the Updated Safety Analysis Report (USAR), and i
delete surveillance requirements for types cf containment penetrations and containment isolation valves which are not incorporated in the DBNPS design.
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2.0 EVALUATION g
i The allowable containment leakage is defined in terms of L where L is the-j l-overall integrated leakage rate.
L is defined as a leaka$e rate of 0.50%
(byweight))ofthecontainmentairShenthecontainmentispressurizedto I
28 psig (P,The containment leakage is comprised of two components:
per 24-hour period.
P is the peak safety analysis accident i
pressure.-
.i filtered air and_ unfiltered air or bypass leakage.
Currently the bypass l
1eakage is limited. by_ TS 3.6.1.2c to 0.015_ L._ This TS change proposes -
t increasing the bypass leakage to 0.03 L T$econsequenceoftheproposed f
changeistoincreasethefractionoft$e. containment volume released which j
is unfiltered while effectively. reducing the fraction released which is filtered resulting in an increase in the radiological consequences.
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2 The NRC staff performed a confirmatory analysis during the original licensing process using a volue of 3 percent for the rate of bypass leakage.
That analysis is documented in NUREG-0136, Supplemeat 1, " Safety Evaluation Report related to operation of Davis-Besse Nuclear Power Station Unit 1," dated April 1977 Based on the analysis, the NRC staff f ound that the calculated doses met 10 CFR Part 50, Appendix A, General Design Criteria (GDC) 19. " Control Room,"
and 10 CFR Part 100, " Reactor Site Criteria," and were acceptable.
This conclusion is documented in Sections 6.4.1, Radiation Protection Provisions,"
and 15.3.1, " Loss of Coolant Accident," of NUREG-0136, Supplement 1.
The licensee benchmarked thair existing USAR analysis, and then performed a new analysis using the same at sumptions except the bypass leakage was 0.03 L instead of 0.015 L Theevaluat.onshowsthattheincreasedthyroiddosesareinaccord withorle$s. than the dNes that the NRC staff calculated and found acceptable to meet GDC 19 and 10 C 3. Part 100 in NUREG-0136, Supplement 1.
Also, the whole body gamma doses were r evaluated by the licensee to determine the impact of increased iodine release on the whole body gamma dose.
The licensee found that the increase in whole bcdy gamma dose is negligible.
The NRC staff has reviewed the above information.
Based on this review, the NRC staff finds the increase in allowed secondary containment bypass leakage to 0.03 L to be acceptable.
3 The following is a discussion of the administrative changes.
TS Table 3.6-1 is being deleted and a reference is being added to the bases to refer to USAR Section 6.2.4 for the list of secondary containment bypass leakage paths.
This change is similar to License Amendment 147 which relocated the list of containment isolation valves from the TS to the USAR.
Also, in TS 4.6.1.2 references to penetrations using continuous leakage monitoring systems and valves pressurized with fluid from a seal system are being deleted, because DBNPS does not have either of those types of systems. Purely editorial char.ges are also made to TS 4.6.1.2.
The NRC staff has reviewed these proposed changes and finds that they are administrative in nature and 6re acceotable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ohio State official was notified of the proposed issuance of the amendment.
The State official ned no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to fr.stallation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or changes a surveillance requirement.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no
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public comment on such findir.y (56 FR 24219).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
l Pursuant to 10 CFR 51.22(b), no environmental impact statement r environmental assessment need be prepared in connection with tie issuance of the amendment, i
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5.0 CONCLUSION
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The staff has concluded, based on the considerations discussed above, that:
l (1) there is reasonable assurance that the health and safet i
not be endangered by operation in the proposed manner, (2) y of the public will such activities will be conducted in compliance with the Commission's regulations, and (3) the l
issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Jon B. Hopkins, NRR Date: August 23, 1991 l
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