ML17139C427
| ML17139C427 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/23/1984 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17139C426 | List: |
| References | |
| NUDOCS 8406050032 | |
| Download: ML17139C427 (5) | |
Text
SAFETY EVALUATION At~iEN
. 23 F-14 SUSQUEHANNA STE M EL C RIG S
T N, UNIT 1 D
C N
. 50-387 Introduction The licensee in letters dated October ll, 1983; October 24, 1983; and November 4, 1983, proposed changes to the Technical Specifications of the operating license for Susquehanna Steam Electric Station, Unit 1 which are as follows:
(2)
(3)
Change the requirements of Technical Specification 4.7.4.a from "If less than two snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months a25X from the date of the first inspection.", to read "If all snubbers of each type are found OPERABLE during the first inservice visual inspection, the second inservice visual inspection shall be performed at the first refueling outage."
Change Technical Specification 4.7. 1.3 requirements for determining the spray pond OPERABLE.
Changes include average water temperature of the spray pond to less than or equal to 81'F, water level at the overflow weir to be greater than or equal to 678'",
and monitoring water level at the overflow weir at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Change Technical Specification Tables 3.3.2-1 and 3.6.3-1 to reinstate isolation signal "X" on Trip Function l.h., Drywell Pressure-High, in Table 3.3.2-1, deleting RHR-Shutdown Cooling Return/LPCI Injection Valves HV-151F122 A and B from the Automatic Isolation section of Table 3.6.3-1 and adding them to the Nanual Isolation section of the same table, and correcting typographical errors in the description and isolation signals of the Suppression Pool Cooling/Spray Valves HV-151FOll A and B.
Evaluation Technical S ecification 4.7.4.a The snubbers at Susquehanna Unit 1'xperienced a long period during construction and startup testing in which they were exposed to many potential failure mechanisms.
The first inspection of the snubbers revealed zero failures after they had been subjected to more strenuous testing then they would be subjected to during normal operation.
The Standard Technical Specification regarding snubbers has been revised to include similar inspection requirements as proposed by the licensee.
The Technical Specifications for Susquehanna Unit 2 and other recently licensed boiling water reactor facilities have snubber inspection requirements similar to those proposed by the licensee.
The staff finds the proposed change acceptable.
8406050032 840523
,PDR ADOCK 05000387 P
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(2)
Technical S ecification 4.7.1.3 A safety evaluation addressing the changes to spray pond average water temperature, water level, and water level monitoring requirements to determine the spray pond OPERABLE, is contained in Sections 2.4.4 and 9.2.3 of Supplement 6 to the Safety Evaluation Report Relating to the Susquehanna Steam Electric Station, Units 1
and 2.
In summary, the staff concluded that the ultimate heat sink's thermal performance, with the changes proposed by the
- licensee, would comply with Regulatory Guide 1.27 and meet the requirements of General Design Criteria 44.
The licensee's revised analysis of the pond's thermal performance completely ignores the effects of wind speed, which is a substantial conservatism, and still shows generally satisfactory performance.
The staff finds the proposed changes to Technical Specification 4.7. 1.3 acceptable.
(3)
Technical S ecification Tables 3.3.2-1 and 3.6.3-1 The proposed change to Technical Specification Table 3.3.2-1 would add isolation signal "X" on Trip Function 1.b. Drywell Pressure-High.
The addition of isolation signal "X" on Trip Function 1.b.
was originally approved by the NRC staff with the issuance of Amendment 4 to Operating License NPF-14.
With the issuance of Amendment 6 to Operating License NPF-14, the isolation signal "X" on Trip Function 1.b.
was inadvertantly dropped from the table.
The staff concludes the addition of 'isolation signal "X" to Trip Function 1.b. is acceptable and corrects an administrative error.
Technical Specification 3.6.3 addresses the operability of the primary containment isolation valves and Table 3.6.3-1 of Technical Specification 3.6.3, lists the primary containment isolation valves by valve number and function, and lists their respective maximum isolation times and isolation signals.
The licensee proposed a
specification change to delete RHR-Shutdown Cooling Valves HV-151F122 A and B from the Automatic Isolation section of Table 3.6.3-1 and add them to the Manual Isolation section of the same table.
This proposed specification change corrects an administrative error.
The present system design does not include this provision for automatic isolation and was never intended to include this requirement.
The present design with the RHR-Shutdown Cooling valves not isolating on a High Drywell Pressure signal (i.e., isolation signal "2") is consistant with all the recently licensed BWRs and with the CE Standard Technical Specifications.
In addition, Table 3.3.2-1, Isolation Actuation Instrumentation, of the licensee's Technical Specification does not require the RHR-System Shutdown Cooling Mode Isolation to include an isolation on High Drywell Pressure.
The licensee also proposed to add
"-Pressure Equalizing Valve" to the valve title for valves HV-151F122 A and B to clarify the functional description of these valves.
The staff has reviewed the proposed changes and finds them acceptable.
The licensee also proposed a specification change to the isolation signals of the Suppression Pool Cooling/Spray Valves HV-151F011 A
and 8 from isolation signals "8" and "C" (i.e., Reactor Vessel Water Level-Low (Level 2) and Main Stream Line High Radiation, respectively) to isolation signal "G" (i.e., Drywell Pressure-High or Reactor Vessel Water Level-Low (Level 1)).
The proposed change corrects a typographical error.
The present system design provides for isolation signal "G" and was not intended to provide for isolation signals "8" and "C."
The present design with isolation signal "G" is consistent with GE Standard Technical Specifications.
The licensee also proposed a change to the title for valves HV-151F011 A and 8 from "RHR-Suppression Pooling Cooling/Spray" to "RHR-Suppression Pool Cooling/Spray."
This proposed change also corrects a typographical error.
The staff has reviewed these proposed changes and finds them acceptable.
Environmental Consideration We have determined that this amendment does not authorize a change in effluent types or total amount nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that this amendment involves action which is insignificant from the standpoint of environmental impact, and, pursuant to 10 CFR Section 51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on 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 regualations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
NY 2 3 $84