ML20235N528

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Proposed Tech Specs Re Standby Liquid Control Sys & Sodium Pentaborate Solution Temp/Concentration Requirements
ML20235N528
Person / Time
Site: Limerick Constellation icon.png
Issue date: 02/22/1989
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20235N524 List:
References
NUDOCS 8903010269
Download: ML20235N528 (7)
v • d • e


Text

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' ATTACHMENT.2 i

LIMERICK GENERATING STATION Docket No. 50-352-License No. NPF-39 PROPOSED TECHNICAL SPECIFICATIONS CHANGES List of Attached Change Pages v

3/4 1-19 3/4 1-20 3/4 1-21 3/4 1-22 B 3/4 1-4 i

G903010269 DR 890222 *

' ADOCM 05000352 h PNU ji

INDEX LIMITING CONDITIONS FOR OPERATIONS AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 A P P L I C AB I L I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 0- 1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 S H U T D OW N MA RG I N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 1 - 1 3/4.1.2 R E ACT I V I TY AN 0 MAL I E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/ ' 1-2 3/4.1.3 CONTROL RODS Control Rod Operability....................................... 3/4 1-3 Control Rod Maximum Scram Insertion Times..................... 3/4 1-6 Control Rod Average Scram Insertion Times..................... 3/4 1-7 Four Control Rod Group Scram Insertion Times.................. 3/4 1-8 Control Rod Scram Accumulators................................ 3/4 1-9 Control Rod Drive Coupling....................'................ 3/4 1-11 Control Rod Position Indication............................... 3/4 1-13 Control Rod Drive Housing Support............................. 3/4 1-15 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer........................................... 3/4 1-16 Rod Block Monitor............................................. 3/4 1-19 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM................................. 3/4 1-19 Figure 3.1.5-1 Sodium Pentaborate Solution Temperature / Concentration Requirements.............................. 3/4 1-21 Figure 3.1.5-2 Deleted...(LEFT BLANK INTENTIONALLY)...... 3/4 1-22 l

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.................... 3/4 2-1 Figure 3.2.1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) j Versus Average Planar i Exposure Initial Core Fuel )

Types P8CIB278............................ 3/4 2-2 l

l' LIMERICK - UNIT 1 v

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REACTDlITY CONTROL SYSTEMS .;

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'3/4.1.5 ' STANDBY LI0'UID CONTROL SYSTEM

= LIMITING CONDITION FOR OPERATION 3.1.5 The standby liquid control system, consisting of a minimum of two pumps and

-corresponding flow paths, shall be OPERABLE.

APPLICABILITY: ' OPERATIONAL CONDITIONS 1, 2,.and 5*

' ACTION:

a. In OPERATIONAL CONDITION 1 or 2:
1. With only one pump and corresponding explosive valve OPERABLE, restore one inoperable pump and corresponding explosive valve to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2. With the standby liquid control system otherwise inoperable, restore J the system to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT '

SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. In OPERATIONAL CONDITION 5*: -
1. With only one pump and corresponding explosive valve OPERABLE, restore one inoperable pump and corresponding explosive valve to OPERABLE status within 30 days or insert all insertable control rods within the next hour.
2. With the standby liquid control system otherwise inoperable, insert all insertable control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.5 The standby liquid control system shall be demonstrated OPERABLE:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying that:
1. The temperature of the sodium pentaborate solution is within the j limits of Figure 3.1.5-1.
2. The available volume of sodium pentaborate solution is at least 4537 l gallons. j
3. The heat tracing circuit is OPERABLE by determining the temperature of the pump suction piping to be greater than or equal to 70 F.

I !MEfilCK - UNIT 1 3/4 1-19

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l'tEACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. At least once per 31 days by:
1. Verifying the continuity of the explosive charge.
2. Determining by chemical analysis and calculation
  • that the available weight of sodium pentaborate is greater than or equal to 5389 lbs; the concentration of sodium pentaborate in solution is less than or equal to 13.8% and within the limits of Figure 3.1.5-1 and; the following equation is satisfied:

C x >

Q - 1 13% wt. 86 gpm where C = Sodium pentaborate solution (% by weight)

Q = Two pump flowrate, as determined per surveillance requirement 4.1.5.C.

3. Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c. Demonstrating that, when tested pursuant to Specification 4.0.5, the minimum flow requirement of 41.2 gpm per pump at a pressure of greater than or equal to 1190 psig is met.
d. At least once per 18 months during shutdown by:
1. Initiating at least one of the standby liquid control system loops, including an explosive valve, and verifying that a flow path from the pumps to the reactor pressure sessel is available by pumping demineralized water into the reactor vessel. The replacement charge for the explosive valve shall be from the same manufactured batch as the one fired or from another batch which has been certified by having one of that batch successfully fired. All injection loops shall be tested in 3 operating cycles.

l

2. ** Demonstrating that all heat traced piping is unblocked by pumping from the storage tank to the test tank and then draining and flushing the piping with demineralized water.
3. Demonstrating that the storage tank heaters are OPERABLE by verifying that expected temperature rise of the sodium pentaborate solution in the storage tank after the heaters are energized.  !
  • This test shall also be performed anytime water or boron is added to the U

solution or when the solution temperature drops below 70 F.

    • This test shall also be performed whenever all three heat tracing circuits have been found tn be inoperable and may be performed by any series of se-quential, overlapping or total flow path steps such that the entire flow path is included.

LIMERICK - UNIT 1 3/4 1-20

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. CONCENTRATION, % BY WEIGHT l

l SODIUM PENTABORATE SOLUTION TEMPERATURE / CONCENTRATION REQUIREMENTS FIGURE 3.1.5-1 LIMERICK - UNIT 1 3/4 1-21  !

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THIS PAGE LEFT BLANK INTENTIONALLY O

J' LIMERICK - UNIT 1 3/4 1-22 l

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3/6.1 RfACTSMHTY CCHTROL SYSTEN$

BASES 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM The standby liquid control system provides a backup capability for bringing the '

reactor from full power to a cold, Xenon-free shutdown, assuming that the withdrawn control rods remain fixed in the rated power pattern. To meet this objective it is necessary to inject a quantity of baron which produces a concentration of 660 ppm in the reactor core and other piping systems connected to the reactor vessel. To allow  !

for potential leakage and improper mixing, this concentration is increased by 25%.

The required concentration is achieved by having available a minimum quantity of 4,537 gallons of sodium pentaborate solution containing a minimum of 5,389 lbs. of sodium pentaborate. This quantity of solution is a net amount which is above the [

pump suction shutoff level setpoint thus allowing for the portion which cannot be i injected. The pumping rate of 41.2 gpm provides a negative reactivity insertion rate over the permissible solution volume range, which adequately compensates for the positive reactivity effects due to elimination of steam voids, increased water density from hot to cold, reduced doppler effect in uranium, reduced neutron leakage from boiling to cold, decreased control rod worth as the moderator cools, and xenon decay. The temperature requirement ensures that the sodium pentaborate always remains in solution.

With redundant pumps and explosive injection valves and with a highly reliable control rod scram system, operation of the reactor is permitted to continue for short periods of time with the system inoperable or for longer periods of time with one of the redundant components inoperable.

The SLCS system consists of three separate and independent pumps and explosive valves. Two of the separate and independent pumps and explosive valves are required to meet the minimum requirements of this technical specification and, where applicable, satisfy the single failure criterion.

The SLCS must have an equivalent control capacity of 86 gpm of 13% weight sodium pentaborate in order to satisfy 10 CFR 50.62 (Requirements for reduction of risk from anticipated transients without scram (ATWS) events for light-water-cooled nuclear power plants). This equivalency requirement is fulfilled by having a system which satisfies the equation given in 4.1.5.b.2.

The upper limit concentration of 13.8% has been established as a reasonable limit to prevent precipitation of sodium pentaborate in the event of a loss of tank heating, which would allow the solution to cool.

Surveillance requirements are established on a frequency that assures a high reliability of the system. Once the solution is established, boron concentration will not vary unless more boron or water is added, thus a check on the temperature and volume once each 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the solution is available for use.

Replacement of the explosive charges in the valves at regular intervals will assure that these valves will not fail because of deterioration of the charges.

1. C. J. Pione, R. C. Stirn and J. A. Woolley, " Rod Drop Accident Analysis for Large BWR's," G. E. Topical Report NE00-10527, March 1972.
2. C. J. Paone, R. C. Stirn, and R. M. Young, Supplement 1 to NED0-10527, July 1972.
3. J. M. Haun, C. J. Paone, and R. C. Stirn, Addendum 2, " Exposed Cores", Supplement 2 to NED0-10527, January 1973.

I !!!f RITJ mill 1 8 3/4 1-4

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