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.

B.

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

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 l

I G

Standby

• 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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