ML20212J997

Proposed Tech Specs,Reflecting Mods to Standby Liquid Control Sys & Revising Pages iv,115,116,117,118,119,120 & 121 to Achieve More Consistency W/Sts

ML20212J997
Person / Time
Site:	Peach Bottom
Issue date:	01/22/1987
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20212J965	List: ML20212J960 ML20212J975 ML20212J997
References
NUDOCS 8701280410
Download: ML20212J997 (10)

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS __

3.4 STANDBY LIQUID CONTROL SYSTEM -4.4 STANDBY LIQUID CONTROL' SYSTEM Applicability: Applicability:

Applies to the operating status Applies to the curveillance of.the Standby Liquid Control requirements of the Standby System. Liquid Control System.

Objective: Objective:

, To assure the availability of a To verify the operability of system with the capability to the Standby Liquid Control shutdown the reactor a<d maintain System.

the shutdown condition without the

use of control rods.

Specification: Specification:

A. Normal System Availability A. Normal System Availability

, l During periods when fuel ' The operability of the Standby is in the reactor and prior Liquid Control System is

-to startup from a Cold verified by thu performance Condition, the Standby Liquid of the following tests:

Control System shall be operable, l except as specified by 3.4.C. At least once during This system need not be each operating cycle:

operable when the' reactor is in the Cold Condition 1. Check that the setting and Specification 3.3.A of the system relief is met, valves is 1400 <P <1680 Psig.

-115-8701280410 870122 PDR ADOCK 05000277 p PDR

PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM (Cont'd.) (Cont'd.)

l 2. Manually initiate one of the Standby Liquid Control System Pumps and pump demineralized water into the reactor vessel from the test tank.

This test checks explosion of the charge associated with the tested loop, proper operation of the explosive valves, and pump operability. The replacement charges to be installed will be selected from the same manufactured batch as the tested charge.

l 3. Both systems, including both explosive valves, shall be tested in the course of two operating cycles.

B. Normal System Requirements B. Normal System Requirements At all times when the Standby Liquid Control System is required to.be operable, the following conditions shall be met:

1. At least 162.7 lbm Boron-10 1. Boron-10 Quantity: At least must be stored in the Standby once per month calculate and Liquid Control Solution Tank record the quantity of Boron-10 and be available for injection. stored in the Standby Liquid Control Solution Tank.

2. The sodium pentaborate 2. Concentration: At least once solution concentration must per month check and record.

be equal to or less than Also, check concentration 9.82% weight. anytime water or boron is added to the solution.

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM (Cont'd.) (Cont'd.)

3. The Standby Liquid Control System conditions must satisfy the following equation:

C [O h[ E h>l 13%wt.(86gpmfQ9.8% atom /

where, C = Sodium Pentaborate Solution Concentration (1 weight)

Q = Pump Flow Rate (gpm) 3. Pump Flow Rate: At least against a system head of once per month each pump 1225 psig, loop shall be functionally tested by pumping boron solution to the test tank.

At least once per quarter check and record pump flow rate against a system head of 1225 psig.

E = Boron-10 Enrichment (% atom 4. Enrichment: Following each Boron-10) addition of boron to the solution tank, immediately calculate enrichment. Verify results by analysis.

5. Solution Volume: At least l

once per day. check and record.

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANOBY LIQUID CONTROL SYSTEM (Cont'd.) (Cont'd.)

l C. Operation with Inoperable Components l From and after the date that a redundant component is made or found to be inoperable, l Specification 3.4.A shall be considered fulfilled and continued operation shall be permitted provided that the component is returned to to an operable condition within seven days. If this Specifica-tion cannot be met,'the reactor shall be in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and a Cold Shutdown Condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. If Specification 3.4.A and 3.4.B cannot be met, the system shall be restored to an operable status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the reactor shall be placed in Hot Shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in a Cold Shutdown Condition with all operable control rods fully inserted l within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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. ' PBAPS 3.4 BASES C STANDBY LIQUID CONTROL SYSTEM I A. - The conditions under-which the Standby Liquid Control System must provide shutdown capability are identified in the Plant Nuclear Safety Operational Analysis (UFSAR Appendix G). If no more-than one operable control rod is withdrawn, the basic shutdown reactivity. requirement for the core is satisfied and the Standby Liquid Control System is not required. Thus, the basic reactivity requirement for the core.is the primary determinant of when the l Standby Liquid Control System is required.

[ l The purpose of the Standby Liquid Control System is to provide the capability of bringing the reactor from full power to a cold,

xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted. To meet this objective, the Standby 4 Liquid Control System is designed to inject a sufficient quantity of Boron-10 (the boron isotope with the high neutron cross-section) to bring the reactor from full power to a suberitical condition, considering the hot to cold reactivity difference.

l xenon poisoning, etc.

The minimum limitation on the relief valve setting is inten'ded to

, l prevent the recycling of boron solution via the lifting of a i relief valve at too low a pressure. The upper limit on the relief i valve setting provides system protection from overpressure.

The only practical time to fully test the Standby Liquid Control

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System is during a refueling outage. Various components of the system are individually tested periodically, thus making more frequent testing of the entire system unnecessary.

B. In order to satisfy the purpose of the Standby Liquid Control System, a sufficient quantity of Boron-10 must be stored and be

, available for injection into the reactor vessel. The quantity of l Boron-10 required to be stored is sufficient to bring the

, concentration of Boron-10 in the reactor to the point where the

! reactor will be shutdown and to provide an additional 25 percent margin beyond the amount needed to shutdown the reactor to allow l~ for possible imperfect mixing of the chemical solution in the reactor water.

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By limiting the sodium pentaborate solution concentration to equal to or less than 9.82% weight, the solution saturation temperature

-is limited to below 53 degrees F (including a 10 degrees F wargin). Since the ambient temperature is anticipated to always be greater than 53 degrees F, the system pump tests can be ,

conducted by recirculating solution from the Standby Liquid

, Control Solution Tank without concern over the solution

, precipitating in the piping, pumps, and valves.

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The Standby Liquid Control System is also required to meet 10 CFR 50.62 (Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants). The Standby Liquid Control System must have the equivalent control capacity of an 86 gpm system of 13%

weight natural sodium pentaborate in order to satisfy 10 CFR 50.62 requirements. This equivalency requirement is fulfilled by having a system which satisfies the equation given in 3.4.B.3. Each paramet'er (sodium pentaborate solution concentration, pump flow rate, and Boron-10 enrichment) is tested at an interval consistent with the potential for that parameter to vary and also to assure proper equipment performance. Boron-10 enrichment testing is only i

required when chemical addition occurs since change cannot occur by any process other than the addition of new chemicals to the 1

Standby Liquid Control Solution Tank.

The enriched sodium pentaborate solution is made by combining natural borax and Doron-10 enriched boric acid in stoichiometric quantities in demineralized water. Since both the borax and Boron-10 enriched boric acid have known Boron-10 en,richments, the resulting Boron-10 enriched sodium pentaborate also has a known Boron-10 enrichment. This process is adequate for use in determining immediate compliance with 3.4.B.3 following chemical addition. The solution Boron-10 enrichment shall be subsequently verified by analysis to be acceptable.

The volume of solution stored is checked at a frequency to assure high reliability of the system. Solution level is indicated and

, alarmed in the control room.

i- l C. Only one of the two Standby Liquid Control pumping loops is needed for operating the system. One inoperable pumping circuit does not immediately threaten shutdown capability, and reactor operation can continue while the circuit is being repaired.

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'-- PBAPS -

4.4 BASES

, STANDBY LIQUID CONTROL ~ SYSTEM

-The bases for .the surveillance requirements and the details of the various tests are given in Subsection 3.8.5 of the Updated Final Safety Analysis Report.

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I CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing Application were served on the following by deposit in the United States mail, first-class postage prepaid, on this 22nd day of January,1987.

Regional Administrator U.S. Nuclear Regulatory Commission, Region I 631 Park Avenue

. King of Prussia, PA 19406 T. P. Johnson, Resident Inspector U. S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P. O. Box 399 Delta, PA 17314 Mr. Thomas Gerusky, Director Bureau of Radiation Protection Department of Environmental Resources Fulton Bank Building, 5th Floor Third 4 Locusts Streets liarrisburg, PA 17120

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h Eu ne 4. Bradley Attorney for Philadelphia Electric Company