ML20214M789

Proposed Tech Specs Upgrading Requirements for Inservice Insp Surveillance of Reactor Vessel Per Rev 1 to Reg Guide 1.14

ML20214M789
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/31/1986
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20214M764	List: B12159, Application for Amend to License DPR-61,changing Tech Specs to Upgrade Inservice Insp Surveillance Requirements for Reactor Vessel Per Rev 1 to Reg Guide 1.14.Fee Paid ML20214M789
References
RTR-REGGD-01.014, RTR-REGGD-1.014 NUDOCS 8609110281
Download: ML20214M789 (2)

Text

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Docket No. 50-213 Attachment i Haddam Neck Plant Proposed Revisions to Technical Specifications August,1986 8609110281 860904 PDR ADOCK 05000213 P PDR

'A 4.10 INSERVICE INSPECTION AND REACTOR VESSEL SURVEILLANCE Ap.>licability: Applies to the periodic inservice inspection and testing of

. AS VIE Boiler and Pressure Vessel Code Class 1, 2 and 3 equivalent components.

~ Objective: To verify .the structural integrity of the . applicable components defined above.

Specification:

. A. Inservice Inspection of ASME Code Class 1, Class 2 and Class 3 equivalent components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel code and ,

applicable Addenda as required by 10CFR50, Section 50.55a(g), with the exemptions and alternate inspection that have been approved by the NRC pursuant to 10CFR50,' Section 50.55a(gX6Xi). These

! exemptions and alternate inspections are included in the Inservice Inspection Program.

1- B. Inservice testing of ASME Code Class 1, Class 2 and Class 3 equivalent pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel code and l

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applicable addenda as required by 10CFR50, Section 50.55a(g), with the exemptions and alternate testing that have been approved by the

. NRC pursuant to 10CFR50, Section 50.55a(gX6Xi). These exemptions and alternate testing are included in - the Inservice Inspection Program.

C. _ Inservice inspection should be performed for each flywheel as

.follows:

Each reactor coolant pump flywheel shall be inspected per the i -- recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. i i D. The removal plan - for the remaining reactor vessel surveillance capsules is scheduled as follows: ,

t Capsule Capsule Removal Time Predicted Exposure (E IMEV)N Type Incent. Years

• Capsule Reactor Vessel I .H 10 1.3 x 1019 1.0 x 1019 II D 15 2.0 x 1019 1.6 x 1019

{

II E 25 3.3 x 1019 2.6 x 1019 I B Standby j I C Standby I G Standby l

• Remeval time is in approximate calendar years from the date of l initial criticality (July 24, 1967) and intended to coincide with the j nearest refueling outage to that time.

4-20

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