ML20029C220

Proposed Tech Specs 4.4.6.1.3 Re Withdrawal of Reactor Vessel Matl Surveillance Specimens,Per Generic Ltr 91-01

ML20029C220
Person / Time
Site:	Perry
Issue date:	03/15/1991
From:	CENTERIOR ENERGY
To:
Shared Package
ML20029C219	List: ML20029C218 ML20029C220
References
GL-91-01, GL-91-1, PY-CEI-NRR-1313, NUDOCS 9103270016
Download: ML20029C220 (5)

Text

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Attachmen' 1 PY-CEI/NRn .313 L PROPOSED FNPP TECHNICAL SPECIFICATION CHANGES <

70R GENERIC LETTER 91-01 IMPIIMEKTATION i

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j 9103270016 910315 PDR P ADOCK 05000440 PDR 1

REACTOR C001. ANT SYSTEM IN[

SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.1.2 The reactor coolant system temperature and pressure shall be determined to be to the right of the criticality limit _line of Figure 3.4.6.1-1

-curves C and C' within 15 minutes prior to the withdrawal of control rods to bring systemthe reactor to criticality and at least once per 30 minutes during hettup.

4.4.6.1.3 The reactor vessel material surveillance specimens shall be removed and examined to dJttermine changtsAreagonpressure i vMaa

' pro ~'pertdrequiretT~TO'CFR 50, Appendix Crds, .hjar.ial .t. O. N

p.;d_'; ir, Teb'. 0.0.0.1.1-1w The results of these examinations shall be sea to update the curves or Figure 4.4.C 4.4.6.1.4 - The reactor vessel . flango and head flange temperature shell be verified to be greater than or equal to 70'F

a. In OPERATIONA1. CONDITION 4 when reactor coolant system tempe-ature is:

1. 1100*F, at hast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. 5 80'F, at least once per 30 minutes.

'h. .aw'tMnr 30 minutes prior to and at least once per 30 m,..utes during f, "*'tansioning of the reactor vessel heed bolting studs.

g.n PERRY - UNIT 1 3/4 4-20

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TA8 4.4.6.1.3-1 g REAC VESSEL MATERIAL SURVEI E PROGRAM-WITHDRAWAL SCH LE F .

e . \CAFSUL Sgt LEA h0NAWAL TIME 5

w ' NUMBER- LOC FACTO 1/4 T (EFPY) -!

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13108981G1 3a 0.58 10 13108981G1 377 0.58 30 l 13108981G1 .i , 183*'s O.58 Spare

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Attachment 2 PY-CEI/NRR-1313 L

".se 1 of 2 Technical Specification Change to Remove The Reactor Yessel Material Surveillance Program Withdrawal Schedule (Table 4.4.6.1.3-1)

Description of Change Generic Letter 91-01 advised licensees that the subject schedule, Table 4.4.6.1.3-1 (p. 3/4 4-22) in the Perry Technical Specifications, could be {

removed pursuant to the Commission Policy Statement on Technical Specification Improvements. The subject Change Request removes this Table and reference to it from the Technica' Specifications (see Attachment 1 page markings). This proposed change is a supplement to a previous Technical Specification change request regarding the Pressure-Temperature Limits Specification (3.4.6.1).

Other changes described in cur previous change request letter PY-CE1/NRR-ll88L, dated 9/14/90, alsg omit Table references.

This change does not affect plant design or operations as described in the Perry USAR, and does not represent a reduction in regulatory control. 10CFR50 Appendix H/11.B.3 requires prior NRC approval of any changes to the subject schedule and technical justification. A companion letter to this change request, PY-CEI/NRR-1314L (dated 3/15/91) provides this information for NRC approval, and the withdrawal schedule will be retained in the Perry USAR (Sc. : tion 5.3.1.6.1) as a mat ter of docketed record.

Significant -liazards Consideration The standards used to arrive at a determination that a request for amendment invalves no significant hazards considerations are included in the Commission's Regulations, 10CFR50.92, which state that the operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident f rom any previously evaluated, or (3) involve a significant reduction in a margin of safety.

CEI has reviewed the proposed amendment with respect ta these three f actors and has determined that the proposed changes do not involve a significant hazard because:

(1) The proposed change does not involve a significant increase in the

-probability or consequences of a previously evaluated accident; the proposed change remains consistent with the provisions of 10CFR50 Appendices G and H, and its references. Removal of this table from the Technical Specifications and inclusion of the withdrawal schedule in the USAR will not imp h t material surveillance activities and resulting updatas to the minimum reactor vessel metal temperature versus pressure cu: ,e (Specificat. ion 3.4.6.1).

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Attachment 2 PY-CEI/NRR-1313 L Page 2 of '

The reactor vessel surveillance program will continue to incorporate newly derived lead factors, vessel fluence, and temperature shift to revise the withdrawal schedule for the surveillance capsules in accordance with ASTM E185-82. This is merely an administrative program change regarding which document is used to identify the withdrawal schedule. The withdrawal schedule will still exist and receive. prior NRC approval before change. Therefore this proposed change cannot affect either the probability or consequences of any previously evaluated accidents.

(2) The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because the proposed change does not involve any new modes of operation. This is purely an administrative change regarding which document is used to identify the withdrawal schedule. Therefore, no new failure mode or accident sequence is introuuced.

(3) The proposed C..enge does not involve a significant reduction in the margin of safety because the change in the withdrawal schedule documentation is administrative in nature, and will not result in any. change to the reactor vessel material surveillance program itself. Therefore, the proposed change cannot impact any margins of safety.

Environmental Impact Considerations The proposed Technical Specification change has been reviewed against the criteria of-10CFR51.22 for environmental considerations. As shown above, the proposed change does-not involve a significant hazards consideration,- nor increase the types and amounts of-effluents that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. . Based on the foregoing, CEI concludes that the proposed Technical Specification: changes meet the criteria given in 10CFR51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.

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