ML19339B275
| ML19339B275 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/23/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339B272 | List: |
| References | |
| NUDOCS 8011060650 | |
| Download: ML19339B275 (7) | |
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UNITED STATES y
NUCLEAR REGULATORY COMMISslON
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j=1 YANKEE ATOMIC ELECTRIC COMPANY DOCKET N0. 50-29
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YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-3 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The applications for amendment by Yankee Atomic Electric Company (the licensee) dated November 14,1977 (Proposed Change No.156) and March 16,1978 (Proposed Change No.159), comply with the standards and reautrements of the Atomic Energy Act of 1954, as amended (the Act), and the Cormission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will ooerate in confornity with the aoolications, the provisions of the Act, and the rules and regulations of the Commission; 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,.i;d (ii) that such activities will be conducted in compliance with the Cornission's regulations:
D.
The issuance of this amendment will not'be inimical to the common i
defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable require-ments have.been satisfied.
l 2.
Accordinaly, the license is amended by changes to the Technical Soecifications as indicated in the attachment to this license amendment, and'paraaraoh 2.C.(2) of Facility Operating License No.
DPR-3 is hereby amended to read as follows:
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(2) Technical Specifications
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The Technical Specifications contained in Appendix A, as
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revised through Amendment No. 48, are hereby incorporated
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in the license.
The licensee shall operate the facility
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in a cordance with the Technical Specifications.
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This' license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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=t:5 Dennis L. Ziemann-Chief
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Operating Reactors Branch #2
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Division of Operating Reactors
Attachment:
..... l Changes to the Technical Specifications Date of Issuance: May 23,1978
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ATTACHMENT TO LICENSE AMENDMENT NO. 48
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FACILITY OPERATING LICENSE N0. DPR-3 s
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DOCKET NO. 50-29 32-Revise Appendix A-Te:hnical Specifications by removing the following pages and.oserting the enclosed pages.
The revised pages are identified
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REMOVE INSERT 3/4 4-25 3/4 4-25 3/4 5-8 3/4 5-8
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i Overleaf pages (3/4 4-26 and 3/4 5-7) are included for document
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completeness.
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MAIN COOLANT SYSTEM ffh([(
PRESSURIZER l2M;.
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LIMITING CONDITION FOR OPERATION i=:+5
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3.4.8.2 The~ pressurizer temperature shall be:
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a.
Limited to a maximum heatup'of 100 F in any one hour period, l
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Limited to a maximum cooldown of 200 F in any one hour period, l
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c.
Within 225*F of the Main Coolant System temperature, and l
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Greater than 70*F whenever pressurizer pressure exceeds 500 l
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psig.
APPLICABILITY: At'all times.
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ACTION:
With tne pressurizer temperature outside of any of the above limits,
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restore the temperature to within the limits within'30 minutes; perform a r. engineering evaluation to determine the effects of the out-of-limit condition on the fracture toughness-properties of the pressurizer;
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determine tha ; 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 RE')UIREMENTS
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4 4.4.8.2 The pressurizer tecoeratures shall be determined to be within
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the limits:
i a.
At least once per 30 minutes during system heatup or cooldown, and i
b.
.By verifying the 'Aain Coolant System and pressurizer water temperature diffe rential to be within the limit at least once
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per 12. hours dur ng steady state operation, s.;.; _
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YANKEE-ROWE-3/4 4-25 Amendment No. 48
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MAIN COOLANT SYSTEM STRUCTURAL INTEGRITY
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l LIMITING CONDITION FOR OPERATION
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3.4.9 The structural integrity of Main Coolant System components (except i=
steam generator tubes) identified in Table 4.4-3 as Class 1 components 4
i 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
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APPLICABILITY: MODES 1, 2, 3 and 4 A,CTION:
With the structural integrity of any of the above components not con-forming to the above requirements, restore the structural integrity of
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the affected compor.ent to within its limit or isolate the affected 5
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component prior to incratasing the Main Coolant System temperature more
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than 50*F above the minimum temperature required by NOT considerations.
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The provisions of Specification 3.0.4 are not applicable.
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4.4. 9.1 The following inspection program shall be performed during shutdown.
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a.
Inservice Inspections The structural integrity of the Class
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Section XI of the ASME Boiler and Pressure Vessel Code,1970 j
Edition, and Addenda through Winter 1970, as outlined by the
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inspection program shown in Table 4.4-3.
i For all Class 1 piping the ultrasonic calibration shall be per:
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1.
Article III-200 of Appendix III - ASME See XI-Sumer 1976 Addenda except that III-2410 shall be deleted. III-2430 R
4 shall be used except 50% Reference level recording shall
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be perfortned. Ten percent overlap shall be retained.
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2.
Article III-3000 shall be used entirely.
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Article 111-4000 shall be used entirely.
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Supplement 7 shall be used for austenitic welds.
YANKEE-ROWE 3/4 4-26 Amendment No. 42 i
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SURVEILLANCE REQUIREMENTS (Continued)
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Verifying that ECCS recirculation subsystem each pair of
~1 redundant valves a,o purification pumps are aligned to receive electrical power from separate OPERAELE busses, i
Verifying that each ECCS long term hot leg in; ' H:.r sub-system charging pump is aligned to receive elect ' c. '
power from an OPERABLE bus.
9.
Verifying that the long term hot leg injection flow metering instrument is OPERABLE by observing charging flow rate at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
By a visual inspectier: which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to
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establishing containment integrity, and 2.
Of the areas affected within containment at the comple-tion of each containment entry when containnent integrity is established, d.
At least once per 18 months by visual inspection of the con-tainment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Cycling each power operated (excluding automatic) valve
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in the flow path through at least one complete cycle of full travel.
2.
Verifying that valve CS-MOV-532 actuates to its cc---'
position on a safety injection signal.
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SURVEILLANCE REQUIREMENTS (Continued) 4==
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3.
. Verifying that each of the following pumps start auto-MicfME matically upon receipt of a safety injection signal:
12+5 v7 a)
High pressure safety injection (HPSI) pump
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Low pressure safety injection (LPSI) pump a
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Verifying that two low pressure safety injection pumps develop combined flow 2180 gpm. Test every LPSI pump at least once per 36 months.
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Verifying that each charging pump stops automatically upon receipt of-a safety injection signal.
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Verifying that the long term hot leg injection flow meter-ing instrument is OPERABLE by performing a CHANNEL CALIBRATION.
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Verifying that each valve listed in Specification 4.5.2.b.4
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8.
Verifying the proper positioning of the HPSI throttle valves SI-V-671, 672, 673, and 674 by performing an inspectior, 'o insure that:
a)
Each valve locking device is in place and securely welded to the valve handle and to the valve yoke.
4 b)
The scribe mark on each valve body aligns with the scribe mark on the valve yoke.
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At least every 36 months, and/or any time either test under 4.5.e.8 is failed, by developing a backpressure.of 875 psig en in the high pressure safety injectio,n header with two HPSI punps operating as follows:
1.
Pressure to the suction of the HPSI pumps to be 170+
1 10 psi.
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LPSI flow is isolated.
3.
Injection flow is to one loop with the other loops j
isolated by closing the appropriate injection gate valves CS-M0V-536, CS-M0V-537, CS-MOV-538, and CS-MOV 539.
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4.
The' flow to the injection loops shall not be less than dj 200 gpm.
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5.
The above test shall be repeated to include the ope-ation of all HPSI pumps.
7 YANKEE-ROWE 3/4 5-8 Amendment No. A3 48
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