ML20058M901

Amend 165 to License DPR-61,replacing TS Section 4.0.6 of Plant TS, Augmented Inservice Insp Program W/New TS Section 4.0.6, Augmented Erosion/Corrosion Program

ML20058M901
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	09/29/1993
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058M900	List: ML20058M897 ML20058M901 ML20058M905
References
NUDOCS 9310070126
Download: ML20058M901 (11)

Text

,

s ero gi,.

ug$$

i g

UNITED STATES (i

4j NUCLEAR REGULATORY COMQlSSION g

s,,,#

WASHINGT ON, D.C. 20555 0001 CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.165 License No. DPR-61 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated June 22, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.

There is reasonable assurance (i) that the activities authorized by 4

this 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 comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been sati:;fied.

9310070126 930929 ADOCK0500g3 PDR P

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Scecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.165, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

\\.

Jo n F. Stolz, Dir or P oject Directorate I-4 ivision of Reactor Projects - I/II

)

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 29, 1993

)

~..

ATTACHMENT TO LICENSE AMENDMENT NO.165 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert

-1 3/4 0-3 3/4 0-3 3/4 0-4 3/4 0-4 3/4 0-5 3/4 0-5 3/4 0-6 3/4 0-6 3/4 0-7 3/4 0-7 3/4 0-8 3/4 0-8 B3/4 0-6 B3/4 0-6 B3/4 0-6a

i i

APPLICABILITY SURVEILLANCE RE0VIREMENTS (Continued)

{

c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities; d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements; and e.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.0.6 An augmented and modified erosion / corrosion inspection program shall be performed on the following subset of piping:

1) Piping inside the structure that contains the Auxiliary Feedwater pumps (Terry Turbines), 2) the steam piping from the nonreturn valves (MS-NRV-18, 28, 38, and 48) in the structure above the Terry Turbine building to the Terry Turbines and to the Atmospheric Steam Dump Valve (MS-HICV-1201). This program is limited to piping that is greater than one inch nominal size and contains water / steam with operating conditions of 275 psig or greater and/or operating temperatures of 200F or greater.

The augmented inspections shall be consistent with erosion / corrosion l

inspection methodology with selection and performance of inspections on locations based on the ranking of susceptibility to erosion / corrosion wear, with the following additional information considered in the selection process:

Applicable lines with dry steam shall be inspected.

Applicable low usage lines shall be inspected.

A minimum of 5 susceptible components / locations shall be inspected each refueling outage.

Inspections will be conducted to the extent practical within the limitations of design and geometry. An example is the encapsulation sleeves on the steam line and feedwater line elbows inside the Terry Turbine structure. These will not be removed to perform inspections.

HADDAM NECK 3/4 0-3 Amendment No. 165 0164

-2

L i

TABLE 4.0-1 AUGMENTED INSERVICE INSPECTION PROGRAM 5

k.m

. g This page has been deleted zm

' O X

I-G i.

N

-N-O e

t CL

=

M-

'2 O

'D U1 4

t

.s

TABLE 4.0-2 WELD LOCATIONS ON STEAM SUPPLY LINES TO AUXILIARY FEE 0 WATER PUMPS 3g

m 3E This page has been deleted.

x A

n v,

a an 1"

TABLE 4.0-2 33 WELD LOCATIONS ON STEAM SUPPLY LINES TO AUXILIARY FEEDWATER PUMPS 28%

This page has been deleted 2Rn N.

m ia F.

5 TABLE 4.0-2 WELD LOCATIONS ON STEAM SUPPLY' LINES TO AUXILIARY FEEDidATER PUMPS

.x

-% 8, c

E This page has been deleted M-R

?

~

t 5a f

T

,-+-.3-

.-w w

cwr-

+,-a.a we+-...

,%..---vs

..s.4..

+..

,,%4.-.u._m.-.

w-

_v.

er w.ew -a ww w. a. * -...

.r w,,

.w v.

-s.----w-w

Figure 4.0-1 TERRY TURBINE BUILDING This page has been deleted F

i T

HADDAM NECK 3/4 0-8 Amendment No. JJE,16""'

0184

3/4.0 APPLICABILITY BASES (Con't)

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

Soecification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure vessel Code and Addenda as required by 10CFR50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a

clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The requirements of Specifications 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to i

be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

Soecification 4.0.6 The erosion / corrosion program manual specifies and considers all susceptible system piping, including the piping inside the structure that contains the Auxiliary Feedwater pumps (Terry Turbines).

However, some piping is normally excluded from inspections due to usage and steam conditions, since these lines are not considered susceptible to erosion / corrosion.

HADDAM NECK B3/4 0-6 Amendment No.165, 0165

l*.

s 3/4.0 APPLICABILITY BASES (Con't)

To reduce the probability that the Auxiliary Feedwater system will be impacted by a High Energy line Break inside the Terry Turbine buildings an augmented and modified erosion corrosion program has been developed specifically for high energy lines that support the Terry Turbines and would not otherwise be inspected using the existing criteria.

These lines include both the high energy lines physically located in the Terry Turbine building and the steam piping from the nonreturn valves (MS-NRV-18, 28, 38, and 48) in the structure above the Terry Turbines structure to the Terry Turbine and to the Atmospheric Steam Dump Valve (MS-HICV-1201).

The lines included in this augmented and modified erosion / corrosion program are based on the Giambusso criteria for definition of high energy lines.

Specifically, this augmented and modified erosion / corrosion program will include piping greater than one inch in diameter, with temperature limits of 200F or greater and/or pressures of 275 psig or greater.

i HADDAM NECK B3/4 0-6a Amendment No.165, 0145

-- -