ML19312C452
| ML19312C452 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/08/1977 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19312C448 | List: |
| References | |
| NUDOCS 7912130978 | |
| Download: ML19312C452 (3) | |
Text
.
UNITED STATES 8
~'N [..
,'b NUCLEAR REGULATORY COMMISSION (V* f h
WASHINGTOfd. D. C. 20355 t:.a32ff g*s j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMEN 0 MENT NO. 48 TO FACILITY LICENSE NO. OPR-38 AMENDMENT NO. 48 TO FACILITY LICENSE NO. DPR-47 AMENDMENT f;0. 45 TO FACILITY LICENSE NO. OPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNIT N05. 1, 2 AND 3 DOCKET N05. 50-269, 50-270 AND 50-287 Introduction By letter dated May 6,1977, Duke Power Company (licensee) requested a change to the common Technical Specifications incorporated in the operating licenses of Unit Nos.1, 2 and 3 of the Oconee Nuclear Station.
Discussion Section 4.1 of the current Oconee Nuclear Station Technical Specifications requires that a calibration check be performed on the Nuclear Instrumentation (NI) channels once per day and that a calibration be performed if the checks shows that the indicated neutron power is different from the thermal power as indicated by the steady state heat balance by more than 2 percent.
A recent review by the licensee, based on recomendations by the fuel vendor (B&W) on NI calibration data at Oconee revealed an instance in This was reported by which the NI was not conservatively calculated.
This situation arose during power ascension from a maintenance shutdown.
Letween 50% and 90% of full power as determined NI was non-conservatively out of calibration by by the heat balance, theThis situation did not adversely affect reactor safety as much as 13.6%.
4
$912130 k N
i -
since actual power was well belcw 100"..
To avoid this situation in the future, the licensee is proposing an increase in the frequency of calibration checks to provide additional assurance that the NI channels do not widely move out of calibration.
The licensee is also proposing to delete the requirement to recalibrate the NI channels when the NI power exceeds core themal power since any difference in this direction would be cons'ervative with respect to reactor protection.
Evaluation We have reviewed the licensee's proposal to increase the frequency of calibration checksof the NI from once per day to once per shif t, and, to delete the requirement to recalibrate the NI when the difference between the NI pcwer and heat balance power is in the conservative direction.
The change in frequency will result,n a check in calibration of the NI three times more of ten than currently being performed by the existing Technical Specifications. We conclude that the additional surveillance will provide additional assurance that the NI is not out of calibration in a non-conservative direction, and is therefore acceptable.
The licensee has also proposed to delete the requirement to perfor.m recalibration of the l'Is when the heat balance power is less than the NI power.
This change would reduce the number of recalibrations the licensee would have to perform, particularly, if the increased frequency of checks resulted in discovery of the NI channels out of calibration.
The existing Technical Specifications require a recalibration even when the powe-difference is in a conservative direr. tion. With this change, there will always be at least equal or greater T.argin between actual thermal conditions and thermal limits compared :o the existing Technical Specifications. We have reviewed the impact of this change on core parameters, such as quadrant tilt, and found the impact to Le insignificant.
Based en our review of these changes, we conclude that they are acceptable.
Environmental Consideration We have determined that these amendments do not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded. that these amendments involve an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 551.5(d)(4) that an environmental impact statement, negnive declaration, or environmental impact appraisal need o
not be prepared in connection with the issuance of these amendments.
-~
. i Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the
]
- public, Date:
October 28, 1977
.i j
i 1
J G
e
UNITED STATES fiUCLEAR REGULATORY CO*WISS10N 00CrET fiOS. 50-269, 50-270 AND 50-287 DUKE POWER CC"PANY h0TICE Of ISSUM;CE OF A.'E:.DMENTS TO FACILITY CPEPA TU.G LILENSES The U.S. ibclear Regulatory Comnission (the Ccrcission) has issued 45 e Facility Coerating License Nos. DPR-33 A.mendment Mos. 43,48 and t
DPR 17, and CPR-55, respectively, issued to Duke Power Company which revised the Tecnnical Specifications for operation of the Oconee Nuclear Station, Unit Nos 1, 2 and 3, located in Oconee County, Soutn Carolina.
The amendrents are effective within 30 days after the date of issuance.
The amendments revise the cocr.on Technical Specifications to increase the check frequency of the power range amplifier to each shift in Technical Specification 4.1 and Table 4.1-1, and, to limit calibration of the pcv.er range amplifier to when the steady-state heat balance power e.vceeds the nuclear instrumentation power by more than 2 percent in Table 4.1-1.
The application for the arendments conplies with the standards and requirements of the Ato:nic Energy Act of 1954, as amended (the A:t),
and the Conr.issica's rules and regulaticns.
The Cccmission has made appropriate finding: as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license ancncrents.
Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
7 f raMT7
~
~
The Commission has determined that the issuance of these amendments will tot result in any significant environmental impact and that pursuant to 10 CFR 851.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in 4
connection with the issuance of these amendments.
For further details with respect to this action, see (1) the application for amendments dated May 6,1977,(2) Amendments Nos. 48,
45 to License Nos. OPR-38, DPR-47 and DPR-55, respectively, 48 and All of these items and (3) the Commission's related Safety Evaluation.
i are available for public inspection at the Commission's Public Document Rocm, 1717 H Street, NW., Washington, D.C. and at the Oconee County 29691.
A Library, 201 South Spring Street, Walhalla, South Carolina copy of items (2) and (3) may be obtained upon request addressed to
- 20555, the U.S. Nuclear Regulatory Commission, Washington, D.C.
Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 28th day of October 1977.
FOR THE NUCLEAR REGULATORY COMMISSION httvlkk
. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors i
l
.w..-