ML18038B068
| ML18038B068 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/07/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18038B067 | List: |
| References | |
| NUDOCS 9412210068 | |
| Download: ML18038B068 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20S5$ 4001 SAFETY EVALUATION BY THE OFFICE OF NUC EAR REACTOR REGULATION RELATED TO AMENDMENT NO.
21 TO FACILITY OPERATING LICENSE NO.
DPR-33 AMENDMENT. NO. 229 TO FACILITY OPERATING LICENSE NO.
DPR-52 AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUC EAR PLANT UNITS I 2
AND 3 DOCKET NOS.
50-259 50-260 AND 50-296
1.0 INTRODUCTION
By letter dated March 18,
- 1993, the Tennessee Valley Authority (the licensee) requested amendments of the technical specifications (TS) for the Browns Ferry Nuclear Plant (BFN) Units 1, 2,
and 3.
The proposed revisions consist of changes deleting fuel cycle-specific requirements, corrections of administrative errors, correcting discrepancies between the technical specifications bases
.and the BFN Final Safety Analysis Report (FSAR),
and clarification of certain requirements to ensure consistent application.
2.0 EVAL'UATION The proposed changes consist of various, unrelated, administrative revisions to the BFN TS.
Therefore, items are addressed individually.
- 2. 1 BFN Units 1, 2,
and 3 - Revision to TS 3.6.C.2 For BFN Units 1, 2, and 3 TS 3.6.C.2 reads:
Both the sump and air sampling systems shall be OPERABLE during REACTOR POWER OPERATION.
From and after the date that one of these systems is made or found to be inoperable for any reason, REACTOR'OWER OPERATION is permissible only during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the sump system or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the air sampling system.
The proposed specification reads:
Any time irradiated fuel is in the reactor vessel and reactor coolant temperature is above 212'F, both the sump and air sampling systems shall be OPERABLE.
From and after the date that one of these systems is made or found to be inoperable for any reason, the reactor may remain in operation during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the sump system or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the air sampling system.
ENCLOSURE 94Xmiooaa 94za07 Vi PDR ADOCK 0500025%i P
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BFN TS 1.H defines REACTOR POWER OPERATION as "... any operation in the STARTUP/HOT STANDBY or RUN NODE with the reactor critical and above 1 percent rated power."
The current specification applies at any temperature when the reactor is critical above 1 percent rated power.
The proposed specification applies any time the reactor coolant temperature is above 212'F, regardless of whether the reactor is cr.itical or not.
The licensee proposes to revise the applicability of TS 3.6.C.2 to be consistent with TS 3.6.C.l.
The proposed change is a clarification that requires the leak detection systems to 'be operable when'he leakage rate limits are required to be met and is therefore acceptable.
2.2 BFN Unit 1 Revision to TS Bases 3.9 The licensee proposes to revise the BFN Unit 1 TS Bases 3.9 to state that the loss of one 250 volt shutdown board battery affects normal control power for the associated 480 volt and 4160 volt shutdown board.
This revision reflects the actual plant configuration and is therefore acceptable.
2.3 BFN Unit 2 Deletion of Cycle-Specific Specifications The licensee
- proposes, changes to BFN 'Unit 2 TS Table 3.2.C, the Bases for section 3.2, and to TS 3.5.K and 4.5.K.2.
The changes consist of items applicable only to operation during BFN Unit 2 Cycle 6, which was completed on January 29, 1993.
These items are not relevant to.future plant operations, and so their deletion is acceptable.
2.4 BFN Units 1, 2, and 3 Deletion of TS 6.6 The licensee proposes to delete TS 6.6, "Reportable Event Action," and to revise the TS Table of Contents accordingly.
TS 6.6 requires that reportable events (defined by TS definition 1.Z as any of the conditions specified by 10 CFR 50.73) shall be reported to the NRC and that each event will be reviewed by the Plant Operations Review Committee (PORC), with the results submitted to the Site Director and Nuclear Safety Review Board (NSRB).
Requirements for PORC and NSRB review are redundant to other specifications.
Also, the reference to the, notification of the Site Director is redundant in TS 6.5.1.8 where all activities of the PORC shall be documented and provided to the Site Director.
Therefore, deletion of the'duplicate requirements under TS 6.6, and the corresponding Table of Contents revision is acceptable.
2.5 BFN Units 1, 2, and 3 - Revision of TS 4.7.A.2 Regarding Containment Leak Rates The licensee proposes to delete a reference to the testing standard ANSI N45.4-1972 from TS 4.7.A.2.
The proposed revision still requires the licensee to conform to 10 CFR Part 50 Appendix J which requires ANSI N45.4-1972 and ANSI/ANS 56.8-1987, and is therefore acceptable.
2.6 BFN Units 1, 2, and 3 - deletion of References to the Rod Sequence control System.
These changes were incorporated into Amendments
- 196, 212, and 169 for BFN Units 1, 2, and 3, which included other changes relevant to removal.of Rod Sequence control System.
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2.7 BFN Units 1
and 3
Revision of TS Bases
- 3. 1 The proposed change deletes a'eference to a loss of condenser vacuum scram setting.
This feature was deleted by Amendments
- 118, 113, and 89 for BFN Units 1, 2, and 3.
Appropriate changes to the Bases have already been completed for BFN Unit 2.
The proposed changes are consistent with the current plant design and are therefore acceptable.
2.8 BFN Units 2 and 3
Revision of TS Bases 3.5 The proposed change revises a reference to the BFN Final Safety Analysis Report (FSAR) from sub-section 6.7 to section 6.0.
This correction ensures the Bases reference the appropriate FSAR informati'on, and is acceptable.
2.9 BFN Units 1, 2, and 3 - Correction of TS 3.6.B.3 The current specification includes the word. "of" when the word "or" is correct.
The current TS is not grammatical, and the proposed change corrects this problem, clarifying the specification requirements.
Therefore, the proposed change is acceptable.
2.10 BFN Units 2 and 3 - Correction of TS 4.7.E. 1 The current specification repeats the word '".to," which is grammatically incorrect.
The proposed change deletes the extra "to" which does not change the intent of the specification.
- Therefore, the proposed change is acceptable.
2.11 BFN Units 1, 2, and 3 - Revisions to Headings The licensee proposes to change certain headings within the table of contents and for the corresponding specifications.
The changes do not material,ly affect the current content or requirements of the specifications,,
and are therefore acceptable.
2.12 BFN Units 1, 2, and 3 - Capitalization The licensee proposes to change certain words to all lowercase or all uppercase characters in various specifications.
The proposed changes are:
"INOPERABLE" is changed to lowercase on pages 1.0-4 and 3.3/4.3-12.
"Operable" is changed to uppercase on pages 1.0-4 and 3.4/4.4-4.
A similar change is made on page 3.3/4.3-12 for BFN Unit 1 only.
"Operability" is changed to uppercase on page 1.0-4.
"Refuel or StartUp/Hot Standby Mode" is changed to uppercase on page 1.1/2.1-13.
"Shutdown condition" is changed to uppercase on page 3.4/4.4-4.
"Cold shutdown condition" is changed to uppercase on page 3.5/4.5-19 for BFN Unit '2.
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Words in all uppercase letters are typically terms which are defined by Specification 1.0.
The licensee also proposes to capitalize "Specification" in one application on page 1.0-4.
The proposed changes provide additional consistency-and readability, and does not materially affect the current content or requirements of the specifications, and are therefore acceptable.
2.13 BFN Units 1, 2, and 3 - Revisions Regarding Core Operating Limits Report These changes.
were incorporated into Amendments
- 197, 214, and 170 for BFN Units 1, 2, and 3, respectively, whi'ch include other changes relevant to incorporation of the Core Operating Limits report.
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STATE CONSULTATION 1n accordance with the Commission's regulations, the Alabama State official was notified of the proposed issuance of the amendment.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONS IOERATION The amendments change requirements with respect to installation or use of a facility component located within the restricted area as defined in 10'FR Part 20 and changes the surveillance requirements.
The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration, and there has been no public comment on such finding (58 FR 17296).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth 'in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based upon 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and (3) issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
Joseph F. Williams and Laura Dudes Bated:
December 7, 1994
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