ML20149H160

From kanterella
Jump to navigation Jump to search
Application for Amend to License NPF-62,consisting of 11 Separate Changes,Clarifiying & Enhancing to Tech Specs.Fee Paid
ML20149H160
Person / Time
Site: Clinton Constellation icon.png
Issue date: 02/05/1988
From: Hall D
ILLINOIS POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20149H162 List:
References
DPH-0189-88, DPH-189-88, U-601118, NUDOCS 8802190155
Download: ML20149H160 (7)


Text

_ _ _ -

t b U-601118 L4 7-88(02 - 05)-LP 1A.120 Ill/N0/S POWER 00MPANY CLINTCN PCwER $TATICN. P.O. 8Cx 678. CLINTON. ILLINCIS 61727 DPH-0189-88 February 5, 1988 10CFR50.90 Docket 50-461 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station Proposed Amendment to Facility Operating License NPF-62

Dear Sir:

Pursuant to 10CFR50.90, Illinois Power Company (IP) hereby applies for an amendment of Facility Operating License NPF-62 Clinton Power Station (CPS). In accordance with 10CFR50.30, three signed originals and forty copies of this application are enclosed. In accordance with the requirements of 10CFR50.91(b)(1), a copy of this request for amendment has been sent to the Illinois Department of Nuclear Safety as indicated below.

This amendment consists of eleven separate changes to the Technical Specifications. These changes represent clarifications and enhancements to the Technical 1 Specifications. The attachments to this letter provide a description and justification for the requested changes including bases for no significant hazards consideration.

None of these changes affect IP's ability to safely operate CPS under its current license. These changes to the Technical Specifications are consistent in all material aspects with the FSAR as amended, the Safety Evaluation l Report and its Supplements and the as-built olant. An ' l affidavit supporting certification accompanies this letter. '

l In accordance with the provisions of 10CFR170.12 and )

170.21, IP is enclosing a check made out to the U.S. Nuclear Regulatory Commission in the amount of $150.00 as payment of the application fee for this amendment.

\

OD

' I

. r.ock i gjgj gaggggg # 'o o,c DCD 4 W30

' o U-60ll18 L4 7-88(02 - 05)-LP 1A.120 IP has reviewed the proposed Technical Specification changes against the criteria of 10 CFR 51.22 for the environmental considerations. The proposed change does not involve a significant hazards consideration, significantly  :

increase the types and amounts of effluents that may be released offsite, or significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, IP concludes that the proposed Technical Specification change meets the criteria given in 10 CFR 51.22(c)(9) for a categorical exclusion from the requirement for an Environmental Impact Statement.

S ly ours,

, a1 Vice President KBR/krm -

Attachments cc: NRC Resident Office NRC Region III, Regional Administrator NRC Clinton Licensing Project Manager Illinois Department of Nuclear Safety l

J l

t O Attachment 1 to U-601118 t

STATE OF ILLIN0IS COUNTY OF DEWITT DONALD P. HALL, Being first dul'f sworn, deposes and says: That he is Vice President of Illinois Power Company:

that the provided information to certify that these changes to the Clinton Power Station (CPS) Techaical Specifications are consistent with the CPS - Final Safety Analysis Report, the NRC Safety Evaluation Report and the as-built facility has been prepared under his supervision and directions that he knows the contents thereof and that to the best of his knowledge and belief said request and the facts contained therein are true and correct.

DATED: This J M'day of F

  • 88 Signed: / '

Dohirf6 P. Hall Subscribedandsworntobeforemethis8MdayofFebruary 1988.

PA . + 1 to

/ Notary Public aarriclFt. BEAL" My commiesion expires: tiu,, ,. emngiin NOTARY PUGL't, $?s.Tt OF ILLINotB MY COMMI:s:0* Ex?tAtt 31190 m !/! . 0 1

1

j

' - y

/LL/Ng/g powgg ggyppyy n,qu

'ffgl MCAM, ms 00813187 213187 PAY ONE HUNDREO FIFTY DOLLARS NO CENTS to TMs cactm 0, cATE CMICE AVOUNT NUCLEAR REGULATORY COvvisSION 01-13-88 **********c150.00 WASHINGTON D C 20555 kW'- _ . . . . . . . .

( Q' Tis'@l.!!c*'f.*!!b""'" ,, eis".io

. @&Sh!.','?

" 2 & 3 1 8 7a* : 0?1923695s: t,9..'O 15 2 5 v

~ --

l l

l l l

e

. . - . . ~ . .

o t

Attcchm:nt 2 to U-601118 Pags 1 of 2 Summary of Technical Specification Changes

This is a summary listing of all 11 change packages. Please refer to the individual package for a complete description and justification including the Basis For No Significant Hazards Consideration for each change.

Package No. Description 1

6.8.1 (and others in Section 6.0): Replace "Power Plant Manager" with "Manager - Clinton Pow'er Station."

4 1 2 Table 3.3.7.5-1 item 14: Insert note to allow j' inoperability of containment. isolation valve position-indication when the applicable containment isolation valve is deliberately deactivated in the isolated position (and reopened on an intermittent basis under

- administrative control).

3 Various: Results of Startup Test Program 4 Table 3.3.2-1, items 1.c, 1.f; Table 3.3.3-1, items C.1.a. C.1.b. C.1.ct Clarify the logic (trip system) configuration for the affected channels and j

provide a more detailed indication of which pcwer divisions these channels are associated with at the 4

instrument level.

5 Tables 3.3.2-1, 3.3.2-2, 3.3.2-3, 4.3.2.1-1; Table 3.6.4-1: Delete Containment Building Exhaust Radiation

- High isolation trip' signal to Containment Monitoring (CM) and Process Sampling (PS) valves.

6 Tables 3.3.2-1 and 4.3.2.1-1, item 1.g: Revise the APPLICABLE OPERATIONAL CONDITIONS for the Containment Building Fuel Transfer Pool Ventilation Plenum Radiation - High isolation trip channels.

7 4.7.2.h Insert fan EINs into wording for clarification.

8 Table 3.3.3-2 item C.1.e and Table 3.3.5-2 item d:

Revise values for consistency with redesignated instrument-zero.

1

r n ..

AttechmInt 2 to U-601118 Pego 2 of 2 Package No. Description 9 License Conditions 2.C.6 and 2.E Remove 2.C.6 (hot operating experience for SR0s) from license since its applicability has expired and modify 2 E (security) to reflect current Security Plan information.

10 Table 4.3.1.1-1 item 2.b: Delete Nete (h) associcted ,

with the CRANNEL CHECK requirement for the Flev-Biased Simulated Thermal Power - High trip' channels.

11 Table 3.3.2-2 item 2.h: Revise Trip Setpoint and Allowable Value for some of the Main Steam Line Turbine Bldg. Temp. - High trip channels.

l

\

1 l

  • a Attcchment 3 >

to U-601110 Pegs 1 of 87 PACKAGE NUMBER 1 Description and Justification of Proposed Change ,

This proposed administrative change affects Section 6 of the Technical Specifications. On pages 6-2, 6-13, and 6-14, the position title of i "Power Plant Manager" is used several times. The correct title as used in the rest of the Technical Specifications and in Chapter 13 of the Final Safety Analysis Report (FSAR) is "Manager - Clinton Power ,

Station." These pages should be revised to incorporate the co.rrect title and achieve consistency throughout the Technical Specifications.

Basis For No Significant Hazards Consideration According to 10CFR50.92, a proposed change to the license (Technical Specifications) involves no significant hazards consideration i f operation of the facility in accordance with the proposed change would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated (2) create the '

1 possibility of a new or different kind of accident from any accident 1 previously evaluated, or (3) involve a significant reduction in a nargin of safety. l (1) -The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluat:ed. ,

This is an administrative change to achieve textual consistency between the FSAR and the Technical Specifications and does not affect any existing accident analyses.

(2) The proposed change does not create the possibility of a neu or different kind of accident from any accident previously evaluated.

This is an administrative change and does not affect plant design or operation. Therefore, no new accident scenario has beer created.

(3) The proposed change does not involve a significant reduction in a margin of safety. This is an administrative change only and does not affect a margin of safety.

i I

l \

i l

__ -- _ . , _ _ _ . - , , . _ - . _