ML20215J469

From kanterella
Jump to navigation Jump to search
Notice of Denial of Amend to License NPF-58 & Opportunity for Hearing.Portion of Application for Amend Proposing to Delete Figures 6.2.1-1 & 6.2.2-1 Re Corporate & Unit Organization Charts Denied
ML20215J469
Person / Time
Site: Perry 
Issue date: 06/09/1987
From: Colburn T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215J452 List:
References
NUDOCS 8706250012
Download: ML20215J469 (5)


Text

l 1

7590-01 U.S. NUCLEAR REGULATORY COMMISSION CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.

i DOCKET NO. 50-440 NOTICE OF DENIAL 0F AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR A HEARING 1

The U.S. Nuclear Regulatory Commission (the Commission) has denied in part a request by the licensees for amendment to Facility Operating License N,o. NPF-58, issued to Cleveland Electric Illuminating Company, Duquesne Light Company, 1

Ohio Edison Company, Pennsylvania Power Company and Toledo Edison Company'(the j

licensees), for operation of the Perry Nuclear Power Plant, Unit No. 1 (the facility) located in Lake County, Ohio.

The amendment, as proposed by the licensees, would consist of the following y

changes to the Technical Specifications (Appendix A to Facility Operating-License No. NPF-58):

z (1) Reference to specification 3.7.9.1 in Definition 1.18, Fuel Handling Duilding (FHB) Integrity, would be ch'anged to specification 3.7.7.1.

l This'will-correct a typographical error.

9 (?) Table 3.8.4.1-1 would be changed to correctly identify the overcurrent m

N

1..W

, protection device-for circuit-1R25-B522X as OR25-S153-CB13 rather than e.

h,,

1R25-5153-CB13.

/

N4 l

P j

u

l.

2 i

(3) Charts of The Cleveland Electric Illuminating Company's corporate and unit organizations, Figures 6.2.1-1 and 6.2.2-1, would be deleted and references to them would be changed to indicate their locations in the Perry Final Safety Analysis Report (FSAR).

(4) The words "... the Managers, Perry Plant Departments, approval for..."

would be removed from specification 6.5.3.1.e which presently includes the requirement that " Pursuant to 10 CFR 50.59, NRC approval of items i

involving unreviewed safety questions shall be obtained prior to the Managers, Perry Plant Departments, approval for implementation."

(5) The number and locations of the instruments used to determine the drywell average air temperature would be increased from 6 to 17 in order to obtain a more representative average air temperature when the surveillance i

required by specification 4.6.2.6 is performed, (6) An allowable value of greater than or equal to 151.9 psig would be added to specification 4.5.1.e.2.c for surveillance of the automatic depres-surization system (ADS).

This specification requires, at least once per 18 months, performance of a channel calibration of the safety-related instrument air system low pressure alarm system and verifying an alarm setpoint of greater than or equal to 155 psig on decreasing pressure.

In addition, this proposed change would delete an obsolete footnote pertaining to the high pressure alarm system which was replaced by the low pressure alarm system.

I

3 (7) Surveillance requirement 4.6.5.1.b.3 presently specifies that the opening setpoint for the containment vacuum breaker isolation valve shall be greater than or equal to 0.0 psid and less than or equal to 0.112 psid l

1 (containment to outside containment).

The amendment would substitute 3

0.052 for 0.0 and 0.160 for 0.112 as the bounds for this setpoint.

I l

(8) This change would identify the Unit 2 divisional batteries in Specification 3.8.2.2 as alternative DC power sources for use in shutting down Unit 1.

l l

The licensee's application for the amendment was dated December 15, 1986, l

1 as amended February 10, 1987.

Notice of consideration of issuance of the j

~

l amendment was published in the FEDERAL REGISTER on March 12, 1987 (52 FR 7678).

The portion of the application which proposed deleting Figures 6.2.1-1 and f

6.2.2-1 (corporate and unit organization charts) was denied.

10 CFR Section 50.36(c)(5) requires that the Technical Specifications contain provisions relating to the organization of the licensee.

Since the Commission's effort as part of the generic Technical Specification Improvement Program to allow deletion of certain administrative controls is incomplete, this request is viewed as premature by the Commission and is denied.

The licensees were notified of the Commission's denial of this request by letter dated June 9, 1987.

All other changes requested by the licensees' application have been approved by Amendment No. 6.

Notice of issuance of Amendment No. 6 will be published in the Commission's regular biweekly FEDERAL REGISTER Notice.

l 4

By July 20, 1987, the licensees may demand a hearing with respect to the denial described above and any person whose interest may be affected by this proceeding may file a written petition for leave to intervene.

I A request for a hearing or petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, l

Washington, D.C.

20555, Attention:

Docketing and Service Branch, or may be delivered to the Commission's Public Document Room, 1717 H Strect, N.W.,

Washington, D.C., by the above date.

A copy of the petition should also be sent to the General Counsel-8,ethesda, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, and to Jay Silberg, Esq., Shaw, Pittman, Potts & Trowbridge, 2300 N Street, N.W., Washington, D.C.

20037, attorney for the licensees.

For further details with respect to this action, see (1) the application for amendment dated December 15, 1986, as amended February 10, 1987, and (2) the Commission's Safety Evaluation issued with Amendment No. 6 to NPF-58 dated June 9, 1987, which are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Washington, D.C.,

and at the Perry Public Library, 3753 Main Street, Perry, Ohio 44081.

A copy of item (2) may be obtained upon request addressed to the U.S. Nuclear i

I

5 l

Regulatory Commission, Washington, D.C.

20555, Attention:

Division of Reactor Projects - III, IV, V & Special Projects.

Dated at Bethesda, Maryland this 9th day of June, 1987.

FOR THE NUCLEAR REGULATORY COMMISSION y b~

Timothy G. Colburn, Project Manager Project Directorate III-1 Division of Reactor Projects - III, IV, V

& Special Projects N

f.