ML17139B514

Safety Evaluation Supporting Amend 14 to License NPF-14

ML17139B514
Person / Time
Site:	Susquehanna
Issue date:	04/15/1983
From:	NRC
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ML17139B513	List: ML17139B512 ML17139B514 ML17139B515
References
NUDOCS 8304260088
Download: ML17139B514 (5)

Text

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~ + I SAFETY EVALUATION AMEN

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-14 SUSQUEH Oll, UNIT 1 Introduction The licensee in letters dated December 10, 1982 and Harch ll, 1983, proposed changes to the Technical Specifications of the operating license for Susquehanna Steam Electric Station, Unit 1 which are as follows:

a)

Changes to Technical Specifications 3.9.1 and 4.9.1 to enhance operator awareness of the testing provisions of the reactor mode switch.

b)

Update Technical Specification 4.6.1.7 to conform with design drawings and actual plant configuration.

c)

Correct typographical errors in Figure 83/4 3-1 and to correct various specifications which reference the "Semiannual Radioactive Effluent Release Report" or the "Annual Radiological Environmental Operating Report".

Also included in this amendment are changes to Technical Specifications 6.2.3.2 and 6.3 to add inadvertent line omissions.

Evaluation

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a)

Technical Specifications 3.9.1 and 4.9.1 The reactor mode switch selects the proper interlocks for the operational status of the plant.

As the position of the switch is changed, particular protective functions are either bypassed or taken out of bypass.

During refueling operations, the mode switch is mandated by the Technical Specifications to be locked in the Refueling or Shutdown position.

The Susquehanna, Unit 1, technical specifications, which were based upon the General Electric - Standard Technical Specifications (GE-STS),

permitted testing of the switch interlock functions only during Special Test Exceptions (Sections 3.10.1 and 3.10.3).

The licensee requested a change to permit this testing under the Limiting Condition for Operation for the Reactor tlode Switch (Section 3.9.1) by providing a footnote to the APPLICABILITY section.

The intent of the request was to organize the Susquehanna technical specification so that the exception is to the APPLICABILITY section of 3.9.1 and not as a footnote to the Special Test Exceptions; This was requested to enhance operator awareness of the test exception and to permit the testing under less restrictive conditions.

OFFICEI SURNAME/

OATE$

NRG FORM 318 (10-80) NRCM 0240

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The NRC staff has recognized the need to modify the GE-STS on this matter.

The STS have been amended to meet the intent by placing the exception in the SURVEILLAtICE REgUIREHENTS (Section 4.9.1).

The modification to the GE-STS was discussed with and accepted by the licensee for Sections 3.9.1 and 4.9.1 of the Susquehanna Technical Specifications.

Modification of Susquehanna Technical Specifications 3.9.1 and 4.9.1 to reflect the appropriate GE-STS sections is acceptable to the NRC staff.

c)

Technical Specification 4.6.1.7 In Technical Specification 4.6.1.7, the licensee proposed changes in the azimuth values for the drywell air temperature measurements.

The staff has reviewed the request and finds it acceptable on the basis that the changes do not impact the safe operation of the facility but merely update the technical specification to conformance with design drawings and plant configuration.

Typographical Errors Several typographical errors were noted in Figure 83/4 3-1, and in various specifications which reference the "Semiannual Radioactive Effluent Release Report" or the "Annual Radiological Environmental Operating Report".

The HRC staff has reviewed the changes proposed by the licensee and finds them acceptable on the basis that correction of the typographical errors provides clarification of the affected specifications.

Technical Specifications 6.2.3.2 and 6.3 In Technical specification 6.2.3.2, the following words were added to the end of the paragraph:

"... at least one year of which experience shall be in the nuclear field."

In Technical Specification 6.3, the following words were added to the end of the paragraph:

"... and the Shift Technical Advisor who shall meet or exceed the qualifications r eferred to in Section 2.2.1.b of Enclosure 1 of the October 30, 1979 IIRC letter to all operating nuclear power plants.".

OFFICEI SURNAMEP DATE 0 NRC FORM 318 (10-80) NRCM 0240

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w 3 These changes were made by the NRC staff to add inadvertent line omissions from the original specifications.

These changes were discussed with and agreed to by the licensee, and have been met by the licensee since the issuance of the original license on July 17, 1982.

Environmental Consideration He 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 tie have concluded, based on the considerations discussed above, that:

(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, and (3) such activities will be conducted in compliance with the Commission's regulations 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.

APR16 1983 DL:LB¹2 N

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