ML20079K485
| ML20079K485 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/15/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20079K487 | List: |
| References | |
| DPR-66-A-161, NPF-73-A-040 NUDOCS 9110220303 | |
| Download: ML20079K485 (9) | |
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'o,;p UNIT ED STATES NUCLEAR REGULATORY COMMISSION
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-DUQUESNEiLIGHT COMPANY OHIO _ EDISON COMPANY PENNSYLVANIAPOWER_COMPg
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00,CKET NO.-50-334' BEAVER'VALLE,YJ0WERSTATION, UNIT-NO_1
-AMENDMENT-TO FACILITY OPERATING LICENSE Amenduent No.161 License No. DPR-66 1..
The Nuclear _ Regulatory Comission-(the Comission) has found that:
Ai=
The. application for amendment by Duquesne Light Company, et al.
(the licensee) dated May 6, 1991 complies with the standards and
. requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR -
= Chapter I;.
B.
The' facility will caerate in conformity wi_th the application,-
the provisions of-tie Act, and the rules and-regulations of the Comission; C.
There is reasonnble atsurance (1) that the activities authorized by'this amendment can be conducted without endangering the health-Land safety of the public, and-(ii) that such activities will be cononcted41n compliance with the Commission'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 Consission's regulations and all applicable requirements have been satisfied.-
9110220303 911015 PDR ADOCK 05000334 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indictied in the attachment to this license amendment, and paragraph ?.C.(2) of f acility Operating License 110. DPR-66 is hereby amendW to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised thrcugh Amendment No.161, are hereby incorporated in the 'sicanse.
The licensee shall operate the fecility in accotdance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issear,ce, to be irnplemented within 60 days of issuance.
FOR THE t!0 CLEAR REGULATORY C0tEISS10tt
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. Stolz, Director Pro ett Directorate 1-4
- ision of Reactor Projects - 1/11 Office of tiuclear Reacter Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 15, 1991
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ATTACHMENT _T0_ LICENSE AMENDMENT NO. 161 FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50-33,4 0
Replace the following page of Appendix A Technical Specifications with the enclosed page as indicated. The revised page is identified by amendment number and contains vertical lines indicating t'te areas of change, Remove Insert 3/4 4-23 3/4 4-23
..a
REACTOR COOLANT SYSIf,.M SURVEILLANCE REQUIREMENTS r.-,
4.4.9.1 a.
The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations, b.
The Reactor Coolant System temperature and pressure conditions shall be determined to be to the right of the criticality limit line within 15 minutes prior to achieving reactor criticality, c.
The reactor vessel material irradiation surveillance specimens shall be removed and examined in accordance with
to determine changes in material properties.
The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.
BEAVER VALLEY - UNIT 1 3/4 4-23 Amendment No. H2,142,161 I
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/om a%q'o UNITE D STATE S
' ' 't NUCLEAR REGULATORY COMMISSION g
wAsmNOTON, D. C. 20$55 DUQUESNELIGHT,,C,0MPAtQ OH10 EDISON COMPANY THE CLEVELAND ELECTRIC lttimittATitlG COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. S_0-412 BLAVER VALLEY POWER STATION, UNIT 2 AMENDMENT TO FACJLJ,TJ, ppg,A,TJ!lp,LJ,CE!!SE Amendment tio. 40 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnient by Duquesne Light Company, et al.
(the licensee) dated May 6, 1991 ccmplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and reculations 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 aasura. ; (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 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 public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2 2.
Accordingly, the licenst it amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,andparagraph2.C.(2)ofFacility_OperatingLicense No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contair.ed in Appendix A, as revised through Amendment No. 40, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and ~the Environmental Protection Plan.
3.
This license amendment is effective as of t5e date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
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F. Stolz, Direct r J oject Directorate 1-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes'to the Technical Specifications L
-Date of-Issuance: October 15, 1991 l
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ATTACHMENT _T,0,y,CENSEAMENDMENTNO.40 FACILITY OPERATING LICENSE NO. NPF-73 00CKE1 NO. 50-412 i
Replace the following page of Appendix A Technical Specifications with_the enclosed page as indicated. The revised page is identified by amendment number and_ contains vertical lines indicating the areas of change, Remove Insert r
3/4 4-30 3/4 4-30
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O 20 30 40 50 to 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 1.0 pCi/ gram Dose Equivalent I-131 BEAVER VALLEY - UNIT 2 3/4 4-29
REffIQA COOLANT SYSTEM 3 / 4. 4. 9 PRESSUPE/TEMEERATURE. LIMLTH BEACTOR COOLANT SYETIM LIMITING CONDITION FOR OPERATION m m m_,__.
3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
a.
A maximum heatup et 60*F in any 1-hour period, b.
A maximum cooldown of 100'r in any 1-hour period, and c.
A maximum temperature change of $ 5' F in any 1-hour period during hydrostatic testing operations above system design pressure.
APPLICABILITY:
MODES 1, 2,
J, 4,
and 5.
ACTIOE:
k'ith any of the above limits exceeded, restore the temperature and/or pressure to within -the limit within 30 minutes; perform an analysis to determine the effects of the out-of-limit condition on the fracture toughness properties of the Reactor Coolant System determine that the Reacter coolant System remains acceptable for continued operations 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 RCS T
and pressure to less than 200'r and 500 psig, respectively, within thS following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
a SURVEILLANCE REQUIREMENTS
._ u-4.4.9.1 a.
The Reactor Coolant System temperature and presture shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.
b.
The Reactor Coolant System temperature and pressure conditions shall be determined to be to the right of the criticality limit line within 15 minutes prior to achieving reactor criticality, c.
The reactor-vessel material irradiation surveillance specimens shall be removed and examined in accordance iitr.
to determine changes in material properties.
The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.
BEAVER VALLEY - UNIT 2 3/4 4-30 Miendment No.18, 4r