ML051780256

Tech Spec Pages for Amendment, Reactor Building Closed Cooling Water Pump and Service Water Pump Trip Conditions

ML051780256
Person / Time
Site:	Oyster Creek
Issue date:	06/23/2005
From:	NRC/NRR/DLPM
To:
References
TAC MC6287
Download: ML051780256 (4)

Text

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The low-low-low water level trip point is set at 4'80 above the top of the active fuel and will prevent spurious operation of the automatic relief system. The trip point established will initiate the automatic depressurization system in time to provide adequate core cooling.

Specification 3.1.B.1 defines the minimum number of APRM channel inputs required to permit accurate average core power monitoring. Specifications 3.1.B.2 and 3.1.C.1 further define the distribution of the OPERABLE chambers to provide monitoring of local power changes that might be caused by a single rod withdrawal. Any nearby, OPERABLE LPRM chamber can provide the required input for average core monitoring. A Travelling Incore Probe or Probes can be used temporarily to provide APRM input(s) until LPRM replacement is possible.

Since APRM rod block protection Is not required below 61% of rated power, as discussed in Section 2.3, Limiting Safety System Settings, operation may continue below 61% as long as Specification 3.1.B.1 and the requirements of Table 3.1.1 are met. In order to maintain reliability of core monitoring in that quadrant where an APRM is inoperable, it is permitted to remove the OPERABLE APRM from service for calibration and/or test provided that the same core protection Is maintained by alternate means.

In the rare event that Travelling In-core Probes (TIPs) are used to meet the requirements 3.1.8 or 3.1.C, the licensee may perform an analysis of substitute LPRM inputs to the APRM system using spare (non-APRM input) LPRM detectors and change the APRM system as permitted by 10 CFR 50.59.

Under assumed loss-of-coolant accident conditions and certain loss of offsite power conditions with no assumed loss-of-coolant accident, it is inadvisable to allow the simultaneous starting of emergency core cooling and heavy load auxiliary systems in order to minimize the voltage drop across the ergency buses and to protect against a potential diesel generator overload. The diesel generator load sequence time delay relays provide this protective function and are set accordingly. The repetitive accuracy rating of the timer mechanism as well as parametric analyses to evaluate the maximum acceptable tolerances for the diesel loading sequence timers were considered in the establishment of the appropriate load sequencing.

Manual actuation can be accomplished by the operator and is considered appropriate only when the automatic load sequencing has been completed.

This will prevent simultaneous starting of heavy load auxiliary systems and protect against the potential for diesel generator overload.

Also, the Reactor Building Closed Cooling Water and Service Water pump circuit breakers will trip whenever a loss-of-coolant accident condition exists with a concurrent loss of offsite power. This is justified by Amendment 42 of the Licensing Application which determined that these pumps were not required during this accident condition.

Change: 6 OYSTER CREEK 3.1-7 Amendment No.: 9, 16, 112, 171, 176, 235, 255 01/4/80

TABLE 3.1.1 (CONT'D)

Sheet 10 of 13

o. There are two time delay relays associated with each of two pumps. One timer per pump is for sequence starting (SK1A, SK2A) and one timer per pump Is for tripping the pump circuit breaker (SK7A. SK8A)..

p. Two time delay relays per pump must be OPERABLE.

q. Manual initiation of affected component can be accomplished after the automatic load sequencing iscompleted.

r. Time delay starts after closing of containment spray pump circuit breaker.

s. These functions not required to be OPERABLE with the reactor temperature less than 2120 F and the vessel head removed or vented or during REACTOR VESSEL PRESSURE TESTING.

t. These functions may be inoperable or bypassed when corresponding portions in the same core spray system logic train are inoperable per Specification 3.4 A.

u. These functions not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY Is not required to be maintained.

v. These functions not required to be OPERABLE when the ADS Is not required to be OPERABLE.

w. These functions must be OPERABLE only when Irradiated fuel is Inthe fuel pool or reactor vessel and SECONDARY CONTAINMENT INTEGRITY is required per Specification 3.5.B.

y. Deleted.

z. The bypass function to permit scram reset in the SHUTDOWN or REFUEL MODE with control rod block must be OPERABLE in this mode.

aa. Pump circuit breakers will be tripped in 10 seconds +/-15% during a LOCA with a concurrent Loss of Oftsite Power (LOOP) by relays SK7A and SK8A.

bb. Pump circuit breakers will trip instantaneously during a LOCA with a concurrent Loss of Ofsite Power (LOOP).

cc. Only applicable during STARTUP MODE while OPERATING In IRM range 10.

OYSTER CREEK 3.1-18 Amendment No.: 15,_ 4,60,63,7-1,72,10820,171,208, 255

3.6 Radioactive Effluents A&plicabilitv. Applies to the radioactive effluents of the facility.

Obiective: To assure that radioactive material is not released to the environment in an uncontrolled manner and to assure that the radioactive concentrations of any material released Is kept as low as is reasonably achievable and, in any event, within the limits of 10 CFR part 20.1301 and 40 CFR Part 190.10(a).

Specification:

3.6.A. Reactor Coolant Radioactivity The specific activity of the primary coolant except during REFUEL MODE shall be limited to: Less than or equal to 0.2 microcuries per gram DOSE EQUIVALENT (D.E.) 1-131.

Umiting Condition for Operation

1. Whenever an isotopic analysis shows reactor coolant activity exceeds 0.2 uCVgram DOSE EQUIVALENT (D.E.) 1-131, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Additional analyses shall be done at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the specific activity of the primary coolant is restored to within Its limit. The provisions of Specification 3.0.C.3 are applicable.

2. If the reactor coolant activity is greater than 0.2 microcuries per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram D.E. 1-131, be in at least SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The provisions of Specification 3.0.C.3 are applicable.

3. Annual Reporting Requirement The results of specific activity analyses In which the reactor coolant exceeded the limits of Specification 3.6.A shall be reported on an annual basis. The following information.

shall be included:. (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded until after the radiojodine activity Is reduced to less than the limit; (2) Results of the last isotopic analysis for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after radioiodine activity was reduced to less than the limit. Each result should include date and time of sampling and the radiolodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded until after the radiolodine activity is reduce to less than the limit; (4) Graph of the 1-131 concentration and one other radioiodine Isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and, (5) The time duration when specific activity of the primary coolant exceeded the radioiodine limit.

OYSTER CREEK 3.6-1 Amendment No.: 48 084,1466, 491, 244, 255

4. With the reactor mode switch in Run or Startup position, with:

1. Thermal power changed by more than 15% of rated thermal power in one hour', or

2. The off-gas level, at the SJAE, increased by more than 10,000 microcuries per second In one hour during steady state operation at release rates less than 75,000 microcuries per second, or

3. The off-gas level, at the SJAE, Increased by more than 15% in one hour during steady state operation at release rates greater than 75,000 microcuries per second, take sample and analyze at least one sample, between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change in thermal power or off-gas level and at least once per four hours thereafter, until the specific activity of the primary coolant is restored to within limits.

3.6.B Liquid Radwaste Treatment - RELOCATED TO THE ODCM 3.6.C Radioactive Liquid Storage Applicability: Applies at all times to specified outdoor tanks used to store radioactive liquids.

1. The quantity of radioactive material, excluding tritium, noble gases, and radionuclides having half-lives shorter than three days, contained in any of the following outdoor tanks shall not exceed 10.0 curies:

a. Waste Surge Tank, HP-T-3

b. Condensate Storage Tank

2. Inthe event the quantity of radioactive material In any of the tanks named exceeds 10.0 curies, begin treatment as soon as reasonably achievable, continue it until the total quantity of radioactive material in the tank Is 10 curies or less, and describe the reason for exceeding the limit in the next Annual Effluent Release Report.

3. Specification 3.0.A and 3.0.B do not apply.

3.6.D Condenser Offaas Treatment - RELOCATED TO THE ODCM 3.6.E Main Condenser Offaas Radioactivity

1. The gross radioactivity in noble gases discharged from the main condenser air ejector shall not exceed 0.21/E CVsec after the holdup line where E is the average gamma energy (Mev per atomic transformation).

2. Inthe event Specification 3.6.E.1 is exceeded, reduce the discharge rate below the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least SHUTDOWN CONDITION within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• If there are consecutive thermal power changes by more than 15% per hour, take sample and analyze at least one sample between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the change and at least once per four hours thereafter, until the specific activity of the primary coolant Is restored to within limits.

OYSTER CREEK 3.6-2 Amendment No.18,108,126,166,255