ML20003B435
| ML20003B435 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/09/1981 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.G.1, TASK-TM LOD-81-40-05, LOD-81-40-5, NUDOCS 8102120007 | |
| Download: ML20003B435 (3) | |
Text
A O One First National Plaza. CNcago. libns Commonwealth Edison s
Accress Reply to: Post Office Box 767 Chicago, lihnois 60690 February 9, 1981 Mr. B.J. Youngblood, Chief Licensing Branch 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
LaSalle County Station Unit 1, Training During initial Test Program, NUREG-0737 Item 1.G 1, NRC Docket No 50-373 LOD 81-40-05 Re fe ren ce :
(a)
R.L. Tedesco letter to J.S. Abel; dated January 16, 1981 (b)
D.B. Waters letter to U.S. Regulatory Commission, Attn: D.G. Eisenhut; dated January 31, 1981.
(c)
L.0 DelGeorge letter to B.J. Youngblood; dated November 10, 1981
Dear Mr. Youngblood:
The purpose of this letter is to discuss the LaSalle County Station Unit 1 Initial Test Progran, and the additional tests and training to be accomplished in order to address the criteria delineated in NUREG-0737 Item I.G.1;
" Training During Low Power Testing". This discussion is responsive to the NRC directive relative to augmented testing and training contained in Reference (a).
Furthermore, the materials presented here clarify and supplerent the position documented in Section L.17 of the LaSalle County Station FSAR (Amendment 54).
The Boiling Water Reactor (BWR) Initial Test program to be performed on LaSalle County Unit 1 is described in FSAR Figures 14.2-1 and 14.2-2.
This program is equivalent to that described in Figure 1 of the BWR Owners Group response to item 1.G.I. (reference (b)). The LaSalle County program which was reviewed by the NRC and accepted in August, 1979 contains significant testing volunteered by Commonwealth Edison which exceeds the Regulatory Position of Regulatory Guide 1.68, " Initial Test Programs For Water-Cooled Nuclear Power Plants".
Some of the more significant testing being performed for the primary purpose of providing additional operational training prior to the intiation of ccmmercial service include:
- 1. Reactor Core Isolation Cooling (STP-14 of Table 14.2-2)
A minimum of eight hot and cold system initiations with simulated and actual vessel injections, including operation both from the 9
02120007 g1 V
J B.J. Youngblood Page Two February 9, 1981 control room and the remote shutdown panel and at various reactor operating conditions. These tests are in addition to the normal system operations required as a part of the plant response to other transient tests.
These tests, as shown in Table 14.2-2 can be conducted from 0 to approximately 50% power.
- 2. Turbine / Generator Load Rejection (STP-27 s 31 of Table 14.2-2) in addition to the 100% power load rejection required by R.G 1.68, two additional turbine trip / load reject tests will be conducted.
This is also in addition to the Loss of Turbine-Generator Test with loss of Off-Site Power conducted at 20-30% power.
- 3. Recirculation Flow Control and System Testing (STP-29 & 30 of Table 14.22)
Plant response is tested for step and ramp changes to flow control signals over the full range of power operation, including natural circulation conditions.
This testing was augmented with the primary purpose of providing additional training on the flow control system wnich, though reviewed initially on the Zimmer Station (NUREG-0528) will be put in service first at LaSalle County Unit 1.
In addition to these areas of additional testing, a major commitment has been made by Commonwealth Edison to perform an extended series of Safety / Relief Valve Tests during the LaSalle County Unit I startup. This testing includes a minimum of 30 valve tests (more if statistical confirmation is required) over a three week period for which the plant response to single and multiple valve actuations will be observed, in addition, two single valve extended blowdown tests will be performed with and without suppression pool cooling to evaluate the suppression pool temperature response. This program has been reviewed and accepted by the NRC Staff.
This testing program was documented in Reference (c).
The startup test program is conducted on an around-the-clock basis over a six month period.
Therefore, it is anticipated that as a result of the normal shift rotation schedule and the multiple testing described above, all shift crews which will rotate as a team will receive'approximately equal exposure to the various tests being conducted. A record will be maintained of the startup tests either participated in or observed by each shift crew.
If it appears that one or more of the crews is not being exposed to critical segments of the program, non-critical path tests will be rescheduled to remedy the situation.
In addition, to assure that all crews receive adequate information relative to the results of all tests conductad, the LaSalle County training program has been developed as described in Section L.17 of the LaSalle County FSAR to provide for pretest briefings, post-test debriefings and test result training seminars using actual monitored test results. These results, used for training
e B.J. Youngblood Page Three February 9, 1981 during Unit I testing, will be recorded and used as a basis for future simulator training on the LaSalle County simulator which is expected to be operational prior to Unit 2 startup.
Furthermore, during performance of the startup test program, selected portions of the following tests will be video taped and used during operator training courses.
- 1. STP-23B Loss of Feedwater Heater
- 2. STP-23C Feedwater Pump Trip
- 3. STP-27 Turbine Trip
- 4. STP-28 Remote Shutdown
- 5. STP-30 Recric Pump Trip
- 6. STP-31 Loss of Off Power w/ Turbine Trip It has been on the basis of this very extensive testing program which has already been formally documented in the LaSalle County FSAR that Commonwealth Edison has satisfied the criteria of Task I.G.I.
As was concluded by the NRC Staff in Reference (b), the standard BWR test program to which LaSalle County Unit I will with significant augmentation be subjected already addresses the natural circulation and reduced saturation margin testing prescribed recently as a PWR " low power test program".
However, to provide additional information on plant response under conditions simulating total loss of a.c. power, Commonwealth Edison will perform an additional test of this " blackout" case in a manner outlined in Reference (b). This test is expected to require license variations and technical specification changes due to the fact that the degraded condition to be tested falls far outside the normal operation of the plant and extends the accepted design basis to an event of extremely low probability.
It is for these reasons that this commitment must be conditioned on the performance of a detailed safety-evaluation concurred in by Commonwealth Edison and General Electric and accepted by the NRC under the requirements of 10 CFR 50.59, prior to performance of this test.
In the event you have any questions in this regard, please direct them to this office.
Very trul yours, s
v L.O. DelGeorge Nuclear Licensing Administrator cc: NRC Resident inspector-LSCS L