ML20055G540

Amend 128 to License DPR-61,revising Tech Specs to Reflect Removal of Thermal Shield & Attached Surveillance Capsules

ML20055G540
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/19/1990
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055G539	List: ML20055G538 ML20055G540 ML20055G544 ML20055G546
References
NUDOCS 9007230294
Download: ML20055G540 (7)

Text

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UNITED STATES

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CONNECTICf7 YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.128 License No. DPR-61 1.

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

A.

The application for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated February 16, 1990, as supplemented March 29, May 9, and June 6, 1990, complies with the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),

and the Commission's rules and regulations set forth in 10 CFR Chapter il B.

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

Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 Commission'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 pubile; 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 satisfied, g$72$kh

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

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.128, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the LTechnical 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 oh NF. Stolz, Director Pr ject Directorate I-4 0 ision of Reactor Projects - I/II ffice of Nuclear Reactor Regulatioa

Attachment:

Changes 'e the Technical Specifications Date o' I*,suance: July 19, 1990 i

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ATTACHMENT TO LICENSE AMENDMENT N0. 128 FACILITY OPERATING LICE'IS'E NO. DPR-61 DOCKET NO. 50-213 i

J Replace'the following pages of the Appendix "A" Technical Specirications with i

the enclosed pages. The revised pages are identified by ament, ment number and contain vertical lines indicating the areas of change, Remove insert VIII VIII I

3/4 4-40 3/4 4-40 3/4.4-44 3/4 4-44

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B3/4 4-12 B3/4 4-12 i

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LIMITING CQNQITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION E6E i

3/4.4.C REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.......................

3/4 4-29 l

Operational Leakage.............................

3/4 4-31

,3/4.4.7 CHEMISTRY.........:..........................4..........

3/4 4 33 TABLE 3.4 1 REACTOR COOLANT SYSTEM CHEMISTRY. LIMITS..............

3/4 4-34 TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE RE0VIREMENTS............................

3/4 4-35 3/4.4.8 SPECIFIC ACTIVITY......................................

3/4 4-36 FIGURE 3.4-2 DOSE EQUIVALENT I-131 REACT 03 COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT GF RATED 1HERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACT!VITY GREATER THAN I microcurle/ gram DOSE EQUIVALENT I-131........

3/4 4 37 TABLE 4.4 4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.................................

3/4 4-38 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Re ac tor Cool an t Sy s t em..................................

3/4 4-39 FIGURE 3.4 3 CONNECTICVT YANKEE LIMIT CURVE FOR HYDROSTATIC AND LEAK TESTING APPLICABLE FOR 22.) EFFECTIVE FULL 4

POWER YEARS.........................................

3/4 4-41 FIGURE 3.4 4 CONNECTICVT YANKEE REACTOR COOLANT SYSTEM HEATVP LIMITATIONS FOR 22.0 EFFECTIVE FULL POWER YEARS.....

3/4 4-42 FIGURE 3.4-5 CONNECTICVT YANKEE REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS FOR 22.0 EFFECTIVE FULL POWER YEARS.....

3/4 4-43 g

Pressurizer..................................

3/4 4 45 Low Temperature Overoressure Protection Systems......

3/4 4 46 3/4.4.10 STRUCTURAL INTEGRITY....................................

3/4 4-48 3/4.4.11 REACTOR COOLANT SYSTEM VENTS............................

3/4 4 49 1

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l HADDAM NECK VIII Amendment No. 125, 128 r,

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p SURVEILLANCE REOUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be i.

determined.to be within the limits at least once per 30 minutes during system i

heatup, cooldown, and inservice leak and hydrostatic testing operations.

l 4.4.9.1.2 The. reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties. as iJ required by 10 CFR Part 50, Appendix H..

The results of these examinations l

l shall be used to update figures 3.4 3, 3.4-4 and 3.4 5.

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,,'t Amendment No. 125, 128 HADDAM NECX 3/4 4-40

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Amendment No. 125. 128 l'

HADDAM NECK 3/4 4 44 Y

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kACTORCOOLANTSYSTEM BASES PRESSURE / TEMPERATURE LIMITS (Continued)

Although the pressurizer operates in temperature ranges above those for which there is reason for concern of nonductile failure, operating limits i

are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements.

LOW TEMPERATURE OVERPRESSURE PROTECTION SYSTEMS The OPERABILITY of two spring-loaded relief valves (SLRVs) or an RCS vent opening of greater than 7 square inches ensures that the RCS will be pro-tected from presure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are less tian or equal to 315'F. Either SLRV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either: (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 20'F above the RCS cold leg temperatures, or (2) the start of a charging pump (centrifugal) and it: injection into a water-solid RCS.

The Maximum Allowed SLRV Setpoint for the Low Temperature Overpressure Protection System (OPS) is derived by analysis which models the performance of the OPS assuming various mass input and heat input transients. Operation with a SLRV Setpoint less than or equal to the maximum Setpoint ensures that Appendix G criteria will not be violated with consideration for a maximum pressure overshoot beyond the SLRV Setpoint which can occur as a result of time delays in signal processing and valve opening, instrument uncertain-ties, and single failure. To ensure that mass and heat input transients more severe the.n those assumed cannot occur, Technical Specifications require lockout of all but one charging pump (centrifugal or metering) while in MODES 4, 5, and 6 with the reactor vessel head installed and disallow start of an RCP if sc:ondary temperature is more than 20*F above RCS cold leg temperature.

The Maximum Allowed SLRV Setpoint for the OPS will be updated based on the results of examinations of reactor vessel material ~ irradiation surveillance specimens performed as required by 10 CFR Part 50, Appendix H.

l 3/4.4.10 STRUCTURAL INTEGRITY l

The inservice inspection and testing programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by o

l 10 CFR 50.55a(g) except where specific written relief has been granted by l

the Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).

3/4.4.11 REACTOR COOLANT SYSTEM VENTS Reactor Coolant System vents are provided to exhaust noncondensible gases and/or steam from the RCS that could inhibit natural circulation core L

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HADDAM NECK B3/4 4-12

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