ML20140J433

Proposed Change 5 to SEFOR TS

ML20140J433
Person / Time
Site:	05000231
Issue date:	04/28/1971
From:	GENERAL ELECTRIC CO.
To:
Shared Package
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References
FOIA-97-34 NUDOCS 9705140082
Download: ML20140J433 (6)

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l APPENDIX I PROPOSED CHANGE No. 5 TO THE SEFOR TECHNICAL SPECIFICATIONS l

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3.4.L. - The average rate of change in sodium temperature at the reactor L

ve'ssel outlet shall be equal to or less than 10 F/ hour if the

.6 temperature from an initial steady stato value exceeds 125 F.

9 If the temperature change exceeds _125 F, the overall average rate rhall be less than or equal to 10 F/hr. 'Ihe main primary reactor i

vessel outlet temperature recorder shall be used to verify that this limit has been met.

i 3.4.M.

The reactor vessel outer head bolts shall be pm-loaded when l

the reactor vessel outlet sodium temperature is less than 500 F l

l such that the calculated bolt stress is equal to or less than 4000 psi.

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I 3.4.N.

'1he reactor vessel outer head bolts shall neet the acceptance standards of Paragraph N-322.3 and N-325.3 of Section III using the provisions of Paragraph IS-300 of Section XI of the ASME l

Pressum Vessel Code.

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i 3.4.0.

'Ibe cumulative pemanent elongation of the reactor vessel outer head bolts, as detemined by the annual surveillance neasure-ments, shall not exceed 0.030 inch.

l Proposed Change No. 5 April 28, 1971 l

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. BASES FOR.3.4.L-t The change,in the reactor vessel outlet sodium temperature must be controlled l

l st or below 10*F/hr during heat-up and cool-down of the coolant system, when the temperature change is greater than 125*F, to assure that stress levels in the reactor vessel head bolts remain below the values specified in the ASME Pressure Vessel Code. A rapid change in reactor vessel outlet sodissa l

temperature of up to 125'F, followed by a cool-down such as might occur i

following a reactor scram, is acceptable provided that the rapid temperature I

change is followed by a hold in temperature of sufficient duration to give l

an average rate of 10*F/hr from the initial steady state condition.

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BASES FOR 3.4.M The maxim m bolt stresses during primary coolant temperature transients are a function of bolt pre-load. The pre-load limit established in 3.4.M pro-l l

vides assurance that the outer head bolt stresses associated with the

-limits given in paragraph 3.4.L remain below the ASME code allowable j

values.

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BASES FOR 3.4.N i

The acceptance standards of Paragraphs N-322.3 and N-325.3 of Section III of the ASME Pressure Vessel Code provide assurance that the bolts are l-capable of performing their intended function over the service life of the reactor.

Paragraph IS-300 of Section XI of the ASME Pressure Vessel Code defines the course of action in the event the surveillance specified i

in Paragraphs 4.4.R and 4.4.S results in indications outside the referenced acceptance standards of Section III.

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BASES FOR 3.4.0 1

g The pennanent elongation specified in 3.4.0. results in an average i

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L bolt strain of about 0.002 in/in. Strains of this magnitude have 8

been conservatively evaluated to estimate the significance of this anount.of pennanent deformation. Based on the results presented in Reference 8, a cumulative bolt strain of 0.002 in/in determined by the j

annual surveillance measurements specified in Paragraph 4.4.R. would t

not significantly reduce the capability of the bolts to perfonn their intended Ibnction.

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REFERENCES:

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Ietter, Karl Cohen to Dr. Peter A. Morris, March 17, 1971.

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Three reactor vessel outer head bolts shall be removed annually for visual inspection, dimensional checks and dye penetrant testing.

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4.4.S.

Five reactor vessel outer head bolts shall be inspected annually using ultrasonic testing with straight beam longitudinal scan l

from the top of the bolt.

This inspection may be made with the bolts in place or removed frcxa the reactor. Bolts to be examined l

shall be selected so that all of the outer head bolts are examined within a 10 year period.

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Proposed Oiange No. 5 April 28,1971

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BASES 'FOR 4.4.R and 4.4.S t

Excessive rate of change of primary cooiant temperature may cause permanent

• defonnation of the reactor vessel outer head bolts. The limits given in Paragraphs'3.4.L and 3.4.M are intended to avoid such damage. These I

surveillance items are intended to provide additional assurance that these limits are adequate.

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Proposed Change No. 5 April 28,1971 f

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