ML20002A500
| ML20002A500 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/19/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002A499 | List: |
| References | |
| NUDOCS 8011170379 | |
| Download: ML20002A500 (7) | |
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p UNITO STATES NUCLEAR REGULATORY COMMISSION i
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WASHINGTON, D. C. 20666 5.[$@j YANKEE ATOMIC ELECTRIC COMPANY re DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY OPERATING LICEN3E
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Amendment No. 42 License No. DPR-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The application for amendment by Yankee Atomic Electric Company
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(the licensee) dated August 2,1977, as supplemented August 9, 1977, complies with the standards and requirements of the
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'9 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 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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operaring License No.
DPR-3 is hereby amended to read as follows:
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"(2). Technical Specifications _
The Technical Specifications contained in Appendix A,
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as revised through Amendment No. 42, are hereby 9
incorporated in the license.
The licensee shall operate iR..
the facility in accordance with the Technical Specifications."
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3.
This license amendment is effective as of the date of its issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION
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p A. Schwencer,. Chief 3"
Operating Reactors Branch #1 Division of Operating Reactors
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Attachment:
Changes to the Technical Specifications
[7p Date of Issuance: _ August 19, 1977 i
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.:1 ATTACHMENT 'TO LICENSE AMENDMENT N0.42
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FACILITY LICENSE NO. DPR-3
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DOCKET NO. 50-29 ha.g.g }
. "hhb Revise Appendix A as follows:
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Remove the following pages and insert identically numbered pages.
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3/4-4-25 / 3/4 4-26 3/4 4-27 / 3/4 4-28 f
Marginal. lines indicate _ revised area.
Overleaf pages are provided J::. '-
for convenience.
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MAIN COOLANT SYSTEM PRESSURIZER E
g LIMITING CONDITION FOR OPERATION
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3.4.8.2 The pressurizer tenperature shall be:
a.
Limited to a maximum heatup or cooldown of 200*F in any one hour period, n=_
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b.
Within 225'F of the Main Coolant System temperature, and c.
Greater than 70'F whenever pressurizer pressure exceeds 500 psig.
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APPLICABILITY: At all times.
ACTION:
With the pressurizer temperature outside of any of the above limits, restore the temperature tc within the limits within 30 minutes; perform an engineering evaluation to determine the effects of the out-ef-limit condition on the fracture toughness properties of the pressurizer;
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determine that the pressurizer remains acceptable for continued opera-tion or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS
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4.4.8.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.
The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during manual spray operation.
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YANKEE-ROWE 3/4 4-25
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_ ma MAIN COOLANT SYSTEM STRUCTURAL INTEGRITY
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CLASS I COMPONENTS
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LIMITING CONDITION FOR OPERATION
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3.4.9 The structural integrity of Main Coolant System components (except steam generator tubes) identified in Table 4.4-3 as Class 1 components shall be maintained at a level consistent with the acceptance criteria in Specifications 4.4.9.1, 4.4.9.2, 4.4.9.3 and 4.4.9.4.
APPLICABILITY: MODES 1, 2, 3 and 4 g
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-.CTION:
A With the structural integrity of any of the above components not con-forming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component prior to increasing the Main Coolant System temperature more than 50*F above the minimum temperature required by NDT considerations.
The protisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4. 4. 9.1 The following inspection program shall be performed during shutdown:
a.
Inservice Inspections The structural integrity of the Class 1 components shall be demonstrated by verifying their accept-ability when inspected per the applicable requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1970 Edition, and Addenda through Winter 1970, as outlined by the inspection program shown in Table 4.4-3.
For all Class 1 piping the ultrasonic calibration shall be per:
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1.
Article III-200 of Appendix III - ASME Sec XI-Summer 1976 Addenda except that 111-2410 shall be deleted, III-2430 shall be used except 50% Reference level recording shall
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be performed. Ten percent overlap shall be retained.
2.
Article III-3000 shall be used entirely.
1 3.
Article III-4000 shall be used entirely.
4 4
Supplement 7 shall be used for austenitic welds.
l YANKEE-ROWE 3/4 4-26 Amendment No. 42
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MAIN COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
An initial report of any abnomal degradation of the structural integrity of the Safety Class 1 components detected during the above required inspections shall be made within 10 days after detection and the detailed report shall be submitted pursuant to Specification 6.9.4 within 90 days after completion of the surveillance requirements of this specification.
The Inservice Inspection Program shall be reviewed every 5 years to assure that the equipment, techniques'and procedures being utilized are current and applicable. The results of these reviews shall be reported in Special Reports to the
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Commission pursuant to Specification 6.9.6 within 90 days of compl etion.
b.
Inspections Following Repairs or Replacements The structural integrity of the Main Coolant System shall be demonstrated after completion of all repairs and/or replacements to the system by verifying the repairs and/or replacements meet the requirements of Section XI of the ASME Boiler and Pressure Vessel Code,1970 Edition, and Addenda through Winter 1970, except for all Class 1 piping the ultrasonic calibration shall
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be per:
1.
-Article III-2000 of Appendix III - ASME Sec XI - Summer 1976 except that III-2410 shall be deleted, III-2430 shall be used except 50% Reference level recording shall be performed. Ten percent overlap shall'be' retained.
2.
Article III-3000 shall be used entirely.
3.
Article 111-4000 shall be used entirely.
4.
Supplement 7 shall be used for austenitic welds..
When repairs and/or replacements are made which involve new h
strength welds pn components greater than 2 inch diamiter, the new welds 'shall receive a surface and 100 percent volumetric examination and meet applicable code requirements. When
...5 repairs and/or replacements,are made which involve. new strength welds on components 2 inch diameter or smaller, the new welds shall receive a surface examination and meet applicable code o
requirements.
YANKEE-ROWE 3/4 4-27 Amendment No. 42
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MAIN COOLANT SYSTEM y
SURVEILLANCE REQUIREMENTS (Continued)
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c.
Inspections Following System Opening The structural integrity of the Main Coolant System shall be demonstrated after each closing by performing a leak test, with the system pressurized to at least 2200 psig, in accordance with Section XI of the ASME Boiler and Pressure Vessel Code,1970 Edition, and Addenda through Winter 1970, and the Pressure / Temperature limits of Specification 3.4.8.1.
2.
4.4.9.2 The following inspection program shall be performed at least once per 18 months during shutdown on at least one shroud tube per quad-rant,
a.
Inspect the integrity of the bolts and locking devices in the lower flange at the bottom of the shroud tubes.
b.
Inspect the interface between the shroud tube lower flange and the tie plate for separation.
c.
Inspect the interface between the shroud tube upper flange and the top shroud tube support plate for separation.
d.
Inspect the interface between the top shroud tube support plate and the lower core support plate for separation.
e.
Inspect for abnormalities one of each of the types of bolts per quadrant.
4.4.9.3 The pressurizer interior shall be inspected at least once per 18 months during shutdown using the best available techniques to deter-mine if any change has occurred in the cladding cracks that exist and whether any further cracking of the cladding has taken place.
4.4.9.4 The 2" charging line between CH-MOV-524 and CH-611 A shall be dye penetrant tested at least once per 18 months during shutdown.
YANKEE-ROWE 3/4 4-28
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