ML19317D988
| ML19317D988 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/06/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7912100663 | |
| Download: ML19317D988 (5) | |
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.S Sy letter dated Jana'16l;;1977.=we transmitted to you knendments Mos.
- 41. 41 and 38 for Licenses Nos. OPR-38. DPR-47 and DPR-55 for the Oconee Nuclear Station. Units Nos.1, 2 and 3..
Pages 3.5-8, 3.5-9 and 3.5-11 of the Technical toecifications transmitted vith the amendments contained errors.' Enclosed are. corrected pages.
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6 Duke Power Company July 6, 1977 cc:
Mr. William L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 J. Micheal McGarry, III, Esquire DeBevoise & Liberman 700 Shoreham Building 806-15th Street, NW.,
Washington, D.C.
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Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 i
l Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 Chief, Energy Systems Analyses Branch (AW-459)
Office of Radiation Prograns U. S. Environmental Protection Agency Room 645, East Tower 401 M Street, S. W.
Washington, D. C.
20460 U. S. Envirenmental Protection Agency Region IV Office ATTN: EIS COORDINATOR 345 Coutland Street, N. E.
Atlanta, Georgia 30508 0
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s DUKE POWER COMPANY
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Powra Bun.ntxo 422 Sourn Cuencu Sruzzi. CitAnt.orrr. N. C. 28242 WI LLI A M Q. PAR K E R. J R.
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373-4083 May 13, 1976 3
4 Mr. Norman C. Moseley, Director
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Dear Mr. Moseley:
Pursuant to Sections 6.2 and 6.6.2 of the Oconee Nuclear Station Technical Specif cations, please find attached Reportable Occurrence Report R0-269/76-6.
Ver truly yours, u.2 l.0. %
William O. Parker, r.Q EDB:mmb Attachment CC Director, Office of Management Information arid Program Control y;
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(3) Except as provided in specification 3.5.2.4.b, the reactor shall be brought to the hot shutdown condition within four hours if the quadrant power tilt is not reduced to less than 3.41: Unic I within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.41 Unit 2 I
3.41: Unit 3 b.
If the quadrant cilt exceeds +3.41% Unit i and there is simultaneous 3.41: Unit 2 3.41% Unit 3
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indication of a d==14gned control rod per Specification 3.5.2.2, reactor operation may continue provided power is' reduced to 60%
of the thermal power allowable for the reactor coolant pump combination.
c.
Except for physics test, if quadrant tilt exceeds 9.44% Unit 1,
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9.44% Unit 2 9.44: Unic 3 l
a controlled shutdown shall be initiated imnediately, and the reactor shall be brought to the hot shutdown condition within four hours, d
d.
Whenever the recctor is brought to hot shutdcwn pursuant to 3.5.2.4.a(3) or 3.5.2.4.c.above, subsequent reactor operation 1s permitted for the purpose of =easurement, testing, and l
corrective action provided the thermal power and the power I
l range high flux setpoint allowable for the reactor coolant pu=p combination are restricted by a reduction of 2 percent of full power for each I percent tilt for the max 1=um tilt observed prior to shutdown.
Quadrant power tilt shall be monitored on a * *-", frequency e.
of once every two hours during power operation above 15 percent of rated power.
3.5.2.5 Control Rod Positions Technical Specification 3.1.3.5 does not prchibit the exercising a.
of individual safety rods as required by Table 4.1-2 or apply to inoperable safety red
'd 4 ts in Technical Specification 3.3.2.2.
b.
Except for physics tests, operating red group overlap shall be 25% + 5% between two sequential groups.
If this limit is exceeded corrective neasures shall be taken i=nediately to achieve an accep-I table overlap. Acceptable overlap shall be attained within two hours, u the reactor shall be placed in a hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
12 ept for physics tests or exercising control rods, the control c.
ro. withdrawal limits are specified on Figures 3.5.2-1A1 and.
- 3. 5. 2-1.C, (Unit 1), 3. 5. 2-131, 3. 5. 2-132 and 3. 5. 2-133 (Unit 2),
and 3.5.2-lC1, 3. 5.2-1C2, and 3.5. 2-1C3 (Unit 3) for four pu=p j
operation and on Figures 3.5.2-2A1, 3.5.2-2A2 (Unit 1), 3.5.2-231, 3.5.2-232 and 3.5.2-233 (Unit 2), and 3.5.2-2C1, 3.5.2-2C2, and 3.5.2-2C3 (Unit 3) for three or two puup l
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.i 5-8 41, 41 & 38
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Also, exceptir.g physics tests or exercising control rods, the a *il power shaping control rod artion/
wi thdrawal limits a../ specified on figures 3.5.2-4Al' 3.5.2-4A2 and 3.5.2-4A3 (Unit 1) and on figures 3.5.2-481, 3.5.2-4B2, and 3.5.2.483 (Unit 2).
If the control rod position limits are exceeded,' corrective measures shall be taken immediately to achieve an acceptable control rod position.
An acceptable control rod position shall then be attained within two hours.
The minimum shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.
d.
Except for physics tests, power shall not be increased above the power level cutoff as shown on Figures 3.5.2-1A1, 3.5.2-1A2,3.5.2-1A3, (Unit lj, 3.5.2-131, 3.5.2-1B2, and 3.5.2-133 (Unit 2), and 3.5.2-1C1, 3.5.2-1C2, 3.5.2-1C3 (Unit 3), unless the fo1. lowing requirements are met.
l (1)
The xenon reactivity shall be within 10 percent of the value for operation at steady-state raced power.
(2)
The xenon reactivity worth has passed its final maximum or minimum peak during its approach to its equilibrium value for operation at the power level cutoff.
i l.5.2.6 Reactor power i= balance shall be monitored on a frequency not to exceed two hours during power operation above 40 percent rated poser.
Except for physics tests, imbalance shall be maintained within the envelope defined by Figures 3.5.2-3A1, 3.5.2-3A2, 3.5.2-3AJ, 3.5.3-331, l
3.5.2-332, 3.5.2-333, 3.5.2-3C1, 3.5.2-3C2, and 3.5.2-3C3.
If the is-balance is not within the envelope defined by these figures, corrective
, measures shall be taken to achieve an acceptable imbalance.
If an accep-table imbalance is not achieved within two hours, reactor power shall be reduced until imbalance limits are met.
5.2.7 The control red drive patch panels shall be locked at all times with limited access :: be authorized by the mar.ager or his designated alt e rnat e.
4 3.5-9 Amendments 47, 47 & 44
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If the control rod position limits are exceeded, corrective measures shall be taken i= mediately to achieve an acceptable control rod position.
Acceptable control red position shall then be attained within two hours. The
=4a4=r shutdown margin required by Specification 3.5.2.1 shall be maintained at all times.
d.
Except for physics tests, power shall not be increased above the power level cutoff as shown on Figures 3.5.2-1A1, 3.5.2-1A2 (Unit 1), 3.5.2-131, 3.5.2-132, and 3.5.2-133 (Unit 2), and 3.5.2-ici, 3.5.2-1C2, 3.5.2-Ic3 (Unic 3), unless the following requirements are met.
(1) The xenon reactivih shall be within.10 percent of the value for operation at steady-state rated power.
(2) The xenon reactivity worth has passed its final maxinum or minimu= peak during its approach to its equilibriu= value for operation at the pcwer level cutoff.
3.5.2.6 Reactor power imbalance shall be monitored on a frequency not to-exceed two hours during power operation above,40 percent raced power.
l Except for physics tests, imbalance shall be maintained within the envelope defined by Figures 3.5.2-3A1, 3.5.2-3A2, 3.5.2-331, 3.5.2-3B2, 3.5.2-333, 3.5.2-3c1, 3.5.2-3C2, and 3.5.2-3c3.
If the imbalance is i
not within the envelope defined by these figures, corrective measures shall be taken to achieve an acceptable imbalance.
If an acceptable-(
4=h=1=ece is not achieved within two hours, reactor power shall be l
reduced until imbalance limits are met.
3.5.2.7 The control rod drive patch panels shall be locked at all times 'with li=ited access to be authorized by the canager or his designated alter-nate.
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