ML20053D750
| ML20053D750 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/02/1982 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| 4255N, NUDOCS 8206070284 | |
| Download: ML20053D750 (5) | |
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Commonwealth Edison
) one First Natiorni Plus, Chicago. Ilknois
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O '/ Chicago, Illinois 60690 Addrzss R: ply to: Post Office Box 767
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Jun e 2, 1982 Mr. A. Schwence r, Chie f Licensing Branch #2 Division o f Licensing U.
S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 Request for NRC Approval of Change in Acceptance Criteria for RCIC Startup Test NRC Docket Nos. 50-373 and 50-374 References (a):
License NPF-11, Condition 2. c. (29).
(b):
LaSalle County Station FSAR Table 14.2-112, Reactor Core Isolation Cooling System Startup Te s t (c):
General Electric Startup Test Instruction #14, RCIC System, G.E. Documen t No. 22A572 5, Re v. 1.
Dear Mr. Schwencer:
i In accordance with Reference (a), NRC prior approval is required for ".
(b) Modification of test objectives, methods or acceptance criteria for any test identified in Section 14 of the licensee's Final Safety Analysis Report, as amended as being essential; The purpose of this letter is to request prior approval for a change in the acceptance criteria for the Reactor Core Isolation Cooling System Startup Test, as described in Reference (b).
During the NSSS Vendor review of startup test procedures at LaSalle, it was determined that the revision to Reference (c) had changed the acceptance criteria Level 1.b from "The RCIC turbine shall not trip on overspeed during auto or manual starts" to "The RCIC turbine shall not trip on overspeed or isolate during auto or manual starts."
Accordingly, Commonwealth Edison Company desires to add the words "or isolate" to acceptance criteria Level 1.b o f Reference (b), as shown on the attachment.
It should be noted that i
this change makes the acceptance criteria more restrictive than as previously worded.
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PDR ADOCK 05000373 P
A. Schwencer Ju n e 2, 1982 This change has previously been discussed by Messrs. R. D.
Bishop o f LaSalle Station and B.
Clayton of your staff.
It is requested that the NRC review this request and grant prior approval so that the acceptance criteria f or this test can be revised.
If there are any further questions in this matter, please contact this office.
Enclosed for your use are one (1) signed original and thirty-nine (39) copies of this letter and attachment.
Ve ry truly ' yours,
. C f2)B 2.
C. W. Schroeder Nuclear Licensing Adminstrator 1m Attachment cc:
NRC Resident Inspector - LSCS l
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F LSCS-FSAR AMENDMENT 57 JULY 1981 TABLE 14.2-112 REACTOR CORE ISOLATION COOLING SYSTEM STARTUP TEST PURPOSE To verify the proper operation of the Reactor Core Isolation Cooling (RCIC) system over its expected operating pressure and flow ranges and to demonstrate reliability in automatic start-ing from cold standby when the reactor is at rated pressure conditions.
DESCRIPTION The RCIC system test consists of two manual starts, two hot quick starts, five cold quick starts, and any additional starts needed to complete system tuning.
The two manual starts and the two hot quick starts are condensate storage tank (CST),
injections performed during the first reactor heatup.
One of the manual starts and one of the hot quick starts will be per-formed with the reactor dome pressure at 150 psi.
The other manual start and hot quick start will be performed at rated reactor pressure.
The pump discharge pressure during the above manual and hot starts will be throttled to 100 psi above
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the reactor pressure.
Additional starts will be performed as necessary to complete the initial system tuning.
This initial testing is performed to demonstrate operability and to make initial controller adjustmentr..
The initial system tuning is followed by the first vessel l
injection, beginning with cold RCIC hardware
(" cold" being defined as a minimum of 3 days without prior RCIC operation).
Two additional vessel injections, starting from cold RCIC conditions and with the same controller settings as determined during the first vessel injection, will be performed prior to exceeding 25% rated thermal power.
One of these injections will be done using the controllers at the remote shutdown panel.
The vessel injections are performed to verify the adequacy of the startup transient and to make steady-state controller adjustments.
After the final controller settings are determined, two CST t
l injections are done from cold RCIC conditions.
One CST injec-tion is done with the reactor vessel dome pressure at 150 psi, and the other at rated vessel pressure.
These two cold starts l
provide the benchmark for future surveillance testing.
A demonstration of extended RCIC operation (up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) is to be accomplished at a convenient time during the test program.
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LSCS-FSAR AMENDMENT 57 JULY 1981 TABLE 14.2-112 (Cont'd) 7;>
CAUTION:
During vessel injections all reactor steam admission valves of the main and feedwater turbines are closed whenever reactor power is above the moisture carryover threshold.
ACCEPTANCE CRITERIA Level 1 The average pump discharge flow must be equal a.
to or greater than the 100% rated value after 30 seconds have elapsed from initiation on auto starts at any reactor pressure between 150 psig and rated.
OR :ESOLATE b.
The RCIC turbine shall not trip on overspeed during p
auto or manual starts.
If any Level 1 criteria are not met, the reactor will be allowed to operate only up to a restricted power level, until the l
problem is resolved.
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Level 2 a.
The turbine gland seal condenser system shall be capable of preventing steam leakage to the atmosphere.
b.
In order to provide an overspeed and isolation trip avoidance margin, the transient start first and subsequent speed peaks shall not exceed the l
8 rated RCIC turbine speed.
The speed and flow control loops shall be adjusted c.
so that the decay ratio of any RCIC system related l
variable is not greater than 0.25.
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The Delta-P switch for the RCIC steam supply line l
high flow isolation trip shall be calibrated to actuate at 290% of the maximum required steady-state flow, with the reactor assumed to be near the pressure for main relief valve actuation.
During rated pressure cold quick starts, the e.
margin-to-trip of the turbine steam exhaust pressure shall be at least 10 psi.
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AMENDMENT 57 LSCS-FSAR JULY 1981 TABLE 14.2-112 (Cont'd)
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INITIAL CONDITIONS 1.
All construction tests and preoperational tests are completed and approved.
2.
Demineralized water is available for recirculation pumps suction.
3.
Instrument calibration and integrated loops checks are
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completed.
4.
Flow control valves hydraulic control unit is operational.
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14.2-243a
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