ML19323C758

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Amend 8 to License DPR-6,incorporating Tech Specs Change 45 Re Inservice Structural Surveillance of Primary Sys Components & High Energy Piping Outside Containment.Change 45 Encl
ML19323C758
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
(DPR-06-A-008, DPR-6-A-8)
Issue date: 11/05/1974
From: Goller K
US ATOMIC ENERGY COMMISSION (AEC)
To:
Shared Package
ML19323C736 List:
References
FOIA-80-162 NUDOCS 8005190143
Download: ML19323C758 (5)


Text

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,Y CONSUMCRS POWER CO'!PANY l

DOCKET NO. 50-155 AMENDMENT TO FACILITY OPERATING LICENSE s.

At:endment No. 8 License No. DPR-6 1.

The Atomic Energy Cor::aission (the Comission) has found that:

A.

The filings by the Consumers Power Company (the licensee) dated June 29, 1973, and February 7, 1974, comply with the standards and requirements of the Atomic Energy Act of 1954, as at: ended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by thile amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

There were no rea' nests for a hearing or petition for leave to intervene filed b '. lowing notice of the proposed action.

2.

Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachnent to this license amendment and paragraph 3.B of Facility License No. DPR-6 is hereby amended to read as follows omcc >

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Fors. AEC-?ls (Rev.9 53) AECM 0240 e.*

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Technieni Specifications

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The Technical Specifications contained in Appendix A, as revised, are hereby incorporated in the license.

The licensee shall operate the facility in accordance

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with the Technical Specifications, as revised by issued

!i changes thereto through Change No. 45."

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3.

This license a=endment is effective as of the-date of its issuance.

FOR THE ATONIC ENERGY COMMISSION Original signed by:

Earl R. Goller Karl R. Coller, Assistant Director for Operating Reactors Directorate of Licensing Attachment Change No. 45 to the Technical Specifications Date of Issuances liOV 5 1374 l

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l ATTACIUCT A TO LIC2':SE A!!END5 TNT NO. S

. CHANGE NO. 45 TO TIF. TECHNICAL SPECIFICATFNS s

LICENSE HO. DPR-6 CONSUMERS POWER COMPANY l

DOCKET No. 50-155 1.

Add a new item 3 to paragraph 4.1.2(c) to read as follows:

"3.

The high energy line sections identified in Table 9-3b shall be maintained free of visually observable through-wall leaks.

(a)

If a leak is detected by the surveillance program of 4.6 k., efforts to identify the source of the leak shall be started im:nediately.

(b)

If the source of leakage cannot be identified within eight hours of detection or if the leak is found to be from a break in the sections identified in Table 9-3b, the reactor shall be in a cold shutdown within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />."

2 Change item 9.1 to read as folless:

9.1 APPLICABILITY Applies to in-service structural surveillance of primary system components and high energy piping (outside containment).

3.

Add the following item o to Paragraph 9.3 "e.

The structural integrity of the high energy line sect. ions identified in Table 9.3(b) shall be unintained at the level

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required by Section XI of the ASME Boiler and Pressure Vessel ucde, 1974, Article IWB 3000."

4.

Add to 9.4 Basis the following paragraph:

Intensive analysis and review has shown that there are distinct areas of concern where failure of high energy piping systems could preclude the possibility of a safe cold shutdown using safeguards equipment.

This conclusion is based on utilizing the basic AEC high energy line pipe break criteria.

In the interim period, while the plant is operating, omer >

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Form AEC.3:s (Rev.9-53; AEcM 0240 ees

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it therefore becoms necessary to apply additional ceasures to enhance the detection of piping system weaknessos in order to nitigate the offects of a pipe rupture. The inservice encination and the frequency of inspection will provide a ueans for tinely dotection and need only be in effect until required nodifications are complete.

5.

Add the attached Table 9.3(b) to the end of Section 9.

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Form AEC-3IS (Rev.9-53) AECM 0240 eee

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O Table 9.3(M F

Initial Periodic

_1 tem No.

_111gh Energy Area Examinatien }!ethod Leakane Check **

Frequency 1

Main steam Iine from Volumetric Visual Monthly containmen t.penet ration to turbine stop valve 2

Feedwater line from Volumetric Visual 4

containment penetration Monthly to place of exit from main steam tunnel f

The areas LIIIIe examined shall include the longitudinal and circumferential welds and base metal for one wali thickness beyond the edge of the welds.

3 m6nths of issuance of this change.

The inspections shall be completed within A visual inspection of all suspect welds, areas of.high stress or bending moment.

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