ML20117M419
| ML20117M419 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/07/1996 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20117M420 | List: |
| References | |
| NUDOCS 9606180500 | |
| Download: ML20117M419 (7) | |
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t UNITED STATES j,
j NUCLEAR REGULATORY COMMISSION C
WASHINGTON, D C. 20555-0001 o
49.....,o yJRGJNIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 210 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated April 15, 1996, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized i
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 i
have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 210, 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 its date of issuance and shall be implement'd within 30 days.
e FOR THE NUCLEAR REGULATORY COMMISSION
[Y W" G
Eugene V. Imbro, Director Project Directorate II-l Division of Reactor Projects - I/II 1
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
June 7, 1996 i
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Pt UndTED STATES I
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B NUCLEAR REGULATORY COMMISSION
'f WASHINGTON. D.C. 20555 0001 l
sd VIRGINIA ELECTRIC AND POWER COMPANY D0CKET NO. 50-281 i
SURRY POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE 6
Amendment No. 210 License No. DPR-37 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power
^
Company (the licensee) dated April 15, 1996, 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; 8.
The facility will operate in conformity with the application, 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, 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; i
i 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.
4 i l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, j
and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
(B)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 210, are hereby incorporated in the license. The licensee shall operate the facility in accordance 1
with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
- f f A dr,,
c j
l Eugene V. Imbro, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 7, 1996 l
1 E
3
I ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 210 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 21 0 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paaes Insert Paaes TS 3.12-7 TS 3.12-7 TS 3.12-20 TS 3.12-20 l
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1 8
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TS 3.12 ~
- 5. The allowsole QUADRANT POWER TILT is 2.0c~c and is only applicable while j
operating at THERM AL POWER > 509c.
i If, exce.ot for operation at THERMAL POWER s 50c/c or for physics and control 6.
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rod assembly surveillance testing, the QUADRANT POWER TILT exceeds 2Fe, then:
i Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, either the hot channel factors shall be determined and the 3
a.
Power level adjusted to meet the requirement of Specification 3.12.B.1, or t
- b. The power level shall be reduced from RATED POWER 2% for each percent j
of QUADRANT POWER TILT. The high neutron aux trip setpoint shall be similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3 l
1 If the QUADRANT POWER TILT exceeds 10c7c, the power level shall be c.
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reduced from RATED POWER 2% for each percent of QUADRANT POWER TILT within the next 30 minutes. The high neutron Hux trip setpoint shall be j
similarly reduced within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
i 7.
If, except for operation at THERMAL POWER s 50% or for physics and control l
tod assembly surveillance testing, after a further period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the QUADRANT POWER TILT in Specification 3.12.B.5 above is not corrected to i-less than 29c:
If the design hot channel factors for RATED POWER are not exceeded, an i
a.
evaluation as to the cause of the discrepancy shall be made and a special report i
issued to the Nuclear Regulatory Commission.
i
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- b. If the design hot channel factors for RATED POWER are exceeded and the power is greater than109c, then the high neutron flux, Overpower AT and i
Overtemperature AT trip setpoints shall be reduced 1% for each percent the hot I
channel factor exceeds the RATED POWER design values within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, and the Nuclear Regulatory Commission shall be notified.
Amendment Nos. 210 and 210
4 TS 312-20 A 2cc QUADRANT POWER TILT allows that a 57c tilt might actually be present in the core because of insensitivity of the excore detectors for disturbances near the core center such as misaligned inner control rod assembly and an error allowance. No increase in F occurs with til q
up to 5?c because misaligned control rod assemblies producing such tilts do not extend to the unrodded plane, where the maximum F occurs.
q 4
The QPTR limit must be maintained during power operation with THERMAL POWER > 507 RATED POWER to prevent core power distributions from exceeding the design limits.
Applicability during power operation s 50% RATED POWER or when shut down is not re because there is either insufficient stored energy in the fuel or insufficient energy bein transferred to the reactor coolant to require the implementation of a QPTR limit on the distribution of core power. The QPTR limit in these conditions is, therefore, not important. N that the FNaH and F (Z) LCOs still apply, but allow progressively higher peaking factors at 50%
q
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RATED POWER or lower.
1 The limits of the DNB related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the UFSAR assumptions and have been analyti demonstrated to be adequate to maintain a minimum DNBR which is greater than the desi throughout each analyzed transient. Measurement uncertainties are accounted for in the DNB design margin. Therefore, measurement values are compared directly to the surveillance limits without applying instrument uncertainty.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of temperature and pressure through instrument readout is 4
sufficient to ensure that these parameters are restored to within their limits following load i
1 and other expected transient operation. The measurement of the Reactor Coolant System To Flow Rate once per refueling cycle is adequate to detect flow degradation.
i 4
Amendment Nos. 210 and 210
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