ML20090L923

Proposed Tech Specs Pages 4.2-2 & 4.2-4 Re B-10 Surveillance Schedule

ML20090L923
Person / Time
Site:	Oyster Creek
Issue date:	03/17/1992
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20090L918	List: ML20090L915 ML20090L923
References
NUDOCS 9203230330
Download: ML20090L923 (2)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4

3. Functional test once every 24 months

4. Solution volume and Once/ day temperature check

5. Solution Boron-10 Once every 24 months. Enrich-Enrichment ment analyses shall be received no later than 30 days after sampling. If not received within 30 days, notify NRC (within 7 days) of plans to obtain test results.

F. At specific power operation conditions, the actual control rod configuration will be compared with the expected configuration based upon appropriately corrected past data. This comparison shall be made every equivalent full power month. The initial rod inventory measurement perfor.ned with equilibrium conditions are established efter a refueling or major core alteration will be used as base data for reactivity monitoring during subsequent power operation throughout the fuel cycle.

G. The scram discharge volume drain and vent valves shall be verified open at least once per 31 days, except in shutdown modu *, and shall be cycled at least one complete cycle of full travel at least quarterly.

H. All withdrawn control rods shall be determined OPERABLE by demonstrating the scram discharge volume drain and vent valves OPERABLE. This will be done at least once per refueling cycle by placing the mode switch in shutdown and by verifying that:

a. The drain and vent valves close within 30 seconds after receipt ,

of a signal for control rods to scram, and s.

b. The scram signal can be reset and the drain and vent valves open when the scram discharge volume trip is byp3ssed.

CASIS: The core reactivity limitation (Specification 3.2.A) requires that core reactivity be limited such that the core could be made subcritical at any time during the operating cycle, with the strongest operable control rod fully withdrawn and all other

{ operable rods fully inserted. Compliance with this requirement can be demonstrated conveniently at the time of refueling. Therefore, the demonstration must be such that it will apply tc the entire subsequent fuel cycle. The demonstration is performed with the reactor core in the cold, xenon-free condition and will show

• These valves may be closed intermittently for testing under administrative control.

Corrected: l o, '4/84 0YSTER CREEK 4.2-2 Amendment No.: 64, 74, 75, 124, 141  !

Change: 25 l 920323033b 920317 PDR ADOCK 05000219 p PDF

. 4 Pump operability, boron cencentration, solution temperature and volume of standby liquid control systemN are checked on a frequency consistent with instrumentation checks described _ in Specification 4.1. Experience with similar systems has indicated that the test frequencies are adequate. The only practical time to functionally test the liquid control system is during a refueling outage. The functional test includes the firing of explosive charges to open the shear plug valves and the pumping of uemineralized water into the reactor to assure operability of the system downstream of the pumps, lhe test also includes recirculation of liquid control solution to and from the solution tanks.

Pump operability is demonstrated on a more frequent basis. This test consists-of recirculation of demineralized water to a test tank. A ccntinuity check of the firing circuit on the shear plug valves- is providert by pilot lights in the control room. Tank level and temperature alarms are provided to alert the operator to off-normal conditions.

figure 3.2.1 was revised to reflect the minimum and maximum weight percent of sodium pentaborate solution, and the minimum atom percent of B-10 to meet 10 CFR 50.62(c)(4). Since the weight percent of sodium pentaborate can change with water makeup or water evaporation, frequent surveillances are performed on the solution concentration, volume and temperature. The sodium -

pentaborate is enriched with B-10 _ at the chemical vendor's facility to meet the minimum atom percent. Preshipment samples of batches are analy.ied for B-10 enrichment and verified by an independent laboratory prior to shipment to Oyster Creek. Since the B-10 enrichment will not change while in storage or in the-SLCS tank, the _ surveillance for B-10 enrichment is performed-on a 124 month-interval. An additional requirement has been added to evaluate the solution's capab_ility to meet the original design shutdown criteria whenever the Baron-10 enrichment requirement is not met.

The functional test and other surveillance on components, along with the monitoring instrumentation, gives a _high reliability for standby liquid control system operability.

References (1) FDSAR, Volume II, Figure 111-5-11 (2) FDSAR, Volume I, Section VI-3 (3) FDSAR, Volume I, Section Ill-5 and Volume II, Appendix B l (4) FDSAR, Volume I, Section VI-4

-0YSTER CREEK 4.2-4 Amendment No.: 75, 124 r - , . - ..