ML20040H101

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Application for Amend to License NPF-1,consisting of License Change Application 82,revising Tech Specs to Delete Ref to Part Length Control Rods Installed in Reactor Vessel Head
ML20040H101
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 02/10/1982
From: Withers B
PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20027A730 List:
References
NUDOCS 8202170175
Download: ML20040H101 (4)


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PORTLAND GENERAL ELECTRIC COMPANY EUGENE WATER & ELECTRIC BOARD AND PACIPIC POWER & LIGHT COMPANY TROJAN NUCLEAR PLANT Operating License NPF-1 Docket 50-344 License Change Application 82 This License Change Application requests modification of Technical Specifications contained in Appendix A to Operating License NPF-1 to reflect changes in the Rod Control System for the Trojan Nuclear Plant.

PORTLAND GENERAL ELECTRIC COMPANY By Bart D. Withers Vice President Nuclear Subscribed and sworn to before me this 10th day of February 1982.

9MyCommission htfda),

e Notary Public of Oregon

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8202170175 820210 PDR ADOCK 05000344 p

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' LCA 82 P gh 1 of 3 LICENSE CllANGE APPLICATION 82 The proposed replacement pages to Appendix A of Facility Operating. License NPF-1 are provided as Attachment 1.

A description of these changes follows:

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1) Page 1-3.

Definition 1.13 has been changed to eliminate reference to part length rods.

2) Page 3 /4 1-18 Section 3.1.3.1 has 'oeen changed to eliminate reference to part length rods.
3) Page 3/4 1-19.

Section 4.1.3.1.1 has been changed to eliminate reference to part length rods.

4) Page 3/4 1-20.

Section 3.1.3.2 has been changed to eliminate reference to part length rods.

5) Page 3/4 1-26.

Sections 3.1.3.6 and 4.1.3.6 have been deleted.

6) Page 3/4 2-3.

Section 4.2.1.3 has been changed to eliminate reference to part length rods.

7) Page 3/4 2-6a.

Section 4.2.2.2 has been changed to eliminate reference to part length rods.

8) Page 3/4 2-10 and Page 3/4 2-11.

Section 3.2.4 has been changed to eliminate reference to part length rods.

9) Page 3/4 10-1.

Sections 3.10.1, 4.10.1.1.and 4.10.1.3 have been changed to eliminate reference to part length rods.

10) Page 3/4 10-2.

Section 3.10.2 has been changed to eliminate reference to Section 3.1.3.6, which has been deleted.

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11) Page 3/4 10-5.

Sectlon 3.10.4 has been changed to eliminate, reference to Section 3.1.3.5, which has been deleted.

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12) Page B 3/4 1-4.

Section 3/4.1.3 has been changed to eliminate reference to part length rods.

13) Page B 3/4 2-1.

Section 3/4.2.1 has been changed to eliminate reference to part length rods.

14) Page B 3/4 2-4.

Sections 3/4.2.2 and 3/4.2.3 have been changed to eliminate reference to Section 3.1.3.6, which has been deleted.

15) Page 5-4.

Section 5.3.2 has been changed to eliminate reference to part length rods.

LCA 82 Page 2 of 3 REASON FOR CHANGE Technical Specification 3.1.3.6 requires that all part length rods be fully withdrawn during Operating Modes 1 and 2.

In the past, part length rods have caused abnormal flux shapes and xenon oscillations during rod transients at power which may affect DNB considerations. These changes are now required to allow removal of part length rods during the forth-coming refueling outage. Removal is desired for three reasons:

1) The part length rods serve no functional purpose.

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2) Their removal will provide significant savings on refueling critical path time.

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3) Their removal will provide for simplification of control rod testing and operating procedures.

SAFETY / ENVIRONMENTAL EVALUATION Summary of Change The part length control rods installed in the reactor vessel head will be removed. Thimble plugs will be inserted in the vacated fuel assemblies.

The upart length control rod lead screws will be fully withdrawn and locked out with anti-rotational devices.

Th; power supplies will also be removed.

Effect on Technical Specifications and on the Bases fcr Technical l'

Specifications Revisions to the Technical Specifications and the Bases for the Technical Specifications are required. The applicable Technical Specifications and their Bases which are required to be changed are listed on page 1.

Most all of the. changes to the Technical Specifications and the Bases are editorial and merely delete any references to part length rods. Technical Specification 3.1.3.6 and its associated Surveillance Requirement, 4.1.3.6, and Surveillance Requirement 4.10.1.3 have been deleted entirely.

Removal of the part length rods will not charge numerical calculations for shutdown margin as their value was calculated without taking credit for the part length rods.

The changes to the Technical Specifications and the Bases will not increase the occurrence probability or consequences of an accident or malfunction of safety-related equipment, nor will they increase the possibility of a different type of accident or safety-related equipment malfunction not previously analyzed for in the FSAR, and therefore do not constitute an unreviewed safety question.

Effect on FSAR The follcwing sections, tables, and figures of the FSAR will need to be changed to reflect all or part of the fact that the part length rods

LCA 82 Pega 3 of 3 and their power supplies have been removed, that thimble plugs have been installed in their place and that the lead screws have been fully with-drawn and locked out utilizing anti-rotational devices:

Sections 3.5, 4.1, 4.2.3.1.3,-4.2.3.1.4, 4.2.3.2, 4.2.3.2.1, 4.2.3.2.2, 4.2.3.3.1, 4.2.3.4, 4.2.3.5, 4.3.1.6, 4.3.2.2.2, 4.3.2.2.4, 4.3.2.2.6, 4.3.2.4.3, 4.3.2.5.2, 4.3.2.5.3, 4.3.2.6, 4.3.2.8.4, 4.3.2.8.6, 7.7.1, 7.7.1.2.2, 7.7.1.3.2, 7.7.3.2, 15.2.1.3, 15.2.2.2.1, 15.2. 3.1 and 15.4.6, Tables 4.1-1, 4.3-1 and 7.7-2, and the figures at the end of Sections 4.2 and 4.3.

The rod withdrawal accident analyses described in Section 15 of the FSAR will not be effected by the removal of part length rods. These analyses were based on the withdrawal of full length rods which have over ten times the negative reactivity of the part length reds.

The analyses in Section 3.5 of the FSAR for potential ejection of missiles inside Containment are not ef fected by the removal of part length rods.

The analyses provide for a more conservative condition in that the part length rods are assumed to be installed. There is less of a missile hazard with the part length rods removed and their lead screws fully withdrawn. With the lead screw fully withdrawn, it cannot build up as much momentum prior to a postulated ejection from the core that an inserted lead screw could develop.

Removal of. the part length rods will not increase the occurrence probabil-ity of an accident, malfunction or different type of accident or malfunc-tion of safety-related equipment as analyzed in the FSAR, and therefore does not constitute an unreviewed safety question.

Environmental Ef fects The proposed change will not change effluent types or increase amounts.

No unreviewed environmental matter exists and there will be no significant impact on the environment from this change.

BASIS FOR DETERMINATION OF AMENDMENT CLASS This LCR has been determined to result in a Class II amendment in accordance with the criteria of 10 CFR 170.22. This proposed change does not involve a matter of safety or environmental significance. The fee for a Class II amendment is $1,200.

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