ML20213F591
| ML20213F591 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/10/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213F579 | List: |
| References | |
| NUDOCS 8611140312 | |
| Download: ML20213F591 (4) | |
Text
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o UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT N0. 68 TO FACILITY OPERATING LICENSE N0. NPF-5 GEORGIA POWER COMPANY OGLETRDNPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 2 DOCKET N0. 50-366
1.0 INTRODUCTION
By letter dated July 18, 1986, the licensee proposed changes to clarify and correct Technical Specifications Table 3.6.3-1, " Primary Containment l
Isolation Valves," for the Edwin I. Hatch Nuclear Plant Unit 2.
These changes are the outcome of a comprehensive review of the Technical Specifications Table 3.6.3-1 compared to plant leak rate test and inservice inspection procedures, as-built plant drawings, and Hatch Plant l
Unit 2 FSAR Table 6.2-5, " Lines Penetrating the Primary Containment." On the basis of this review, six areas of proposed changes have been identified.
l 2.0 EVALUATION Proposed Change 1: Delete four primary containment isolation valves from Table 3.6.3-1.
l Fire Protection isolation valves 2T43-F159 and 2T43-F160 and reactor pressure vessel instrumentation line isolation valves 2821-F065 A, B are in lines that have been capped.
The subject valves have been subsequently removed from the plant. Since the lines that contained the removed valves have been capped, containment
' integrity is maintained.
It is, therefore, acceptable to delete the removed valves from Table 3.6.3-1 of the Technical Specifications.
l l
Proposed Change 2: Add 15 primary containment isolation valves to Table 3.6.3-1.
The following valves or blind flanges have been added to Table 3.6.3-1.:
Torus to Drywell Vacuum Breaker Air Cylinder 2T48-F323 A, B, C, D, E F,G,H,I,J,K,L Suppression Pool Purification System Suction Line Blind Flange l
2G51-D001 8611140312 861110 PDR ADOCK 05000366 P
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, Suppression Pool Vent and Purge System Supply Line Blind Flange 2T48-D006 RPV Head Spray Isolation Valve 2E11-F023 HPCI Pump Suction Isolation Valve 2E41-F042 These 15 additional valves or blind flanges have either been added to the plant through design modifications, or existed since plant operation began, but have never been listed in the Technical Specifications even though they were tested per plant procedures and identified as containment isolation valves in the Inservice Inspection Plan. Since this proposed change is conservative by adding 15 additional valves to Table 3.6.3-1 of the Technical Specifications, it is acceptable.
Proposed Change 3: Add or correct part numbers for 16 valves:
The following 16 valves have corrected part numbers or have added part numbers for valves which are presently listed without part numbers:
TIP N Purge Isolation Valves 2
2C51-F3017 2C51-F3012 Core Spray Pressure Instrumentation Line Isolation Valves 2E21-F018 A, B Control Air to Vacuum Breaker Isolation Valves 2T48-F342 A, B, C, D, E, F, G, H, I, J. K, L The change corrects inaccurate information in the present Technical Specification and also provides for easier valve identification. Since the proposed change is a clarification of Table 3.6.3-1 in the Technical Specification, it is acceptable.
Proposed Change 4: Move eight valves from Table 3.6.3-1, Section B (Manual Isolation Valves) to Section A (Automatic Isolation Valves)
The following eight valves have been moved from Section B (Manual Isolation Valves) to Section A (Automatic Isolation Valves):
Drywell Vent and Purge System Isolation Valves 2T48-F334 A, B 2T48-F335 A, B Suppression Pool Vent and Purge System Isolation Valves 2T48-F332 A, B 2T48-F333 A, B
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, The above valves have been modified to actuate on automatic isolation signals as a result of post-TMI requirements. This proposed change corrects Table 3.6.3-1 to the current plant configuration and is, therefore, acceptable.
Proposed Change 5: Move RPV head spray valve from Table 3.6.3-1, Section A (Automatic Isolation Valves) to Table 3.6.3-1, Section C (Other IsolationValves).
The proposed change involves moving valve 2E11-F023, RPV head spray isolation valve from Section A (Automatic Isolation Valves) to Section C (Other Isolation Valves). A plant modification is being made to cut the RPV head spray line and fit it with a blind flange inside containment.
The head spray isolation valve 2E11-F023 will remain as the inboard isolation barrier, and will be deactivated and locked closed. Since valve 2E11-F023 will no longer be an automatic isolation valve, it is acceptable to move it to Section C (Other Isolation Valves) in Table 3.6.3-1.
Proposed Change 6: Change the isolation boundary for the fission product monitoring system sample line.
The fission product monitoring sample isolation valve 2011-F061, which is non-nuclear-grade, is being replaced by 2011-F065, which is nuclear-grade. Since this change meets the criteria for a primary containment isolation valve it is acceptable.
On the basis of our evaluation, we conclude that the proposed changes, which clarify, correct and update the Hatch Nuclear Plant Unit 2 with respect to containment isolation valves, are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to installation or use of a facility component located within the restricted areas as defined in 10 CFR Part 20.
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 should be no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for categoricalexclusionsetforthin10CFR51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of this amendment.
e.
4.0 CONCLUSION
On the basis of the considerations discussed above, the staff has concluded 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.
Principal Contributor:
F. Witt Dated: November 10, 1986
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