ML20215B772
| ML20215B772 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 12/01/1986 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 2457K, NUDOCS 8612120309 | |
| Download: ML20215B772 (4) | |
Text
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/ Address Reply to: Post Omos sox 757 Nd' CNcago, tuinois 60000 0767 December 1, 1986 Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC. 20555
Subject:
Byron Station Unit 2 Braidwood Station Units 1 and 2 Initial Test Program NRC Docket Nos. 50-455. 50-456 and 50-457
Reference:
(a)
October 1, 1986 V.S. Noonan letter to D.L. Farrar (b)
January 31, 1985 T.R. Tramm letter to H.R. Denton (c)
February 11, 1985 T.R. Tramm letter to H.R. Denton
Dear Mr. Denton:
Reference (a) provided a request for additional information based on changes made in the Byron /Braidwood FSAR Amendment #47.
Commonwealth Edison has reviewed this request and our reply is presented in Attachment A.
Please direct any questions concerning these items to this office.
One signed original and fifteen copies of this letter and the attachments are provided for your review.
Very truly yours,
/
we- [A S.
C. Hunsader Nuclear Licensing Administrator
/klj cc:
L. Olshan J.
Stevens
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ATTACHMENT A
.NRC REQUEST FOR ADDITIONAL INFORMATION INITIAL STARTUP PROGRAM, FSAR AMENDMENT 47 l
Item 1.
The acceptance criteria in Table 14.2-82 was changed in FSAR Amendment'47.
The new criteria disregards the sign of the measured power coefficient verification factor by
'taking its absolute value.
This allows the measured power coefficient to be either positive or negative, as long as its magnitude is within 1 50F/t power of the predicted 0
power coefficient verification factor.
This is not acceptable.
Provide the basis for the new criteria or revert back to the criteria in place prior to Amendment 47.
Commonwealth Edison Response l
Table 14.2-82 in Amendment 47 does not permit the power coefficient to be either positive or negative.
It only allows the measured power coefficient verification factor to be either positive or negative.
This change had been filed with the NRC via reference (b), and had been accepted for Byron Unit 1.
Item 2.
Question 423.47 addresses the primary safety and relief valves and the steam generator safety and relief valves in the first part of the.first sentence.
However, reference to the steam generator safety and relief valves was inadvertently omitted from the portion of the sentence that asked you to demonstrate that the capacity of the valves is consistent with the accident analysis assumptions, therefore, answer Question 423.47 as though the words
" steam generator safety and relief valves" were placed after " pressurizer power operated relief valves."
Commonwealth Edison Response The original Commonwealth Edison response to Question 423.47 was initially filed with the NRC, after discussion and understood acceptance, on February 11, 1985 as documented in Reference (c).
This was subsequently followed up much later with FSAR Amendment #47 which included the same response.
This response was acceptable and applied for the 100% Power License for Byron Unit 1 and for the issuance of the Safety Evaluation Report for Braidwood Units 1 and 2.
Because of the required additional testing and/or justifications requested by this item, it is being considered by Commonwealth Edison as a backfit item.
We request that it be treated as such by the NRC prior to issuance to Commonwealth Edison.
- Item 3.
In the test summary of Table 14.2-89 it now states that "the plant will be tripped by manual trip or by initiation of an automatic trip of the generator breakers."
It is not clear how the manual trip will be initiated.
Modify Table 14.2-85 to provide the necessary clarification.
Commonwealth Edison Response Commonwealth Edison believes that the reference to Table 14.2-89 in the first sentence is intended to be 14.2-85.
Commonwealth Edison interprets Table 14.2-85 to mean that the generator breakers will trip either manually or by the initiation of an automatic trip.
We agree with the NRC position, and offer the following clarification.
by manual trip of the generator main breakers or by initiation.
(See attached marked up page) 2457K J
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TABLE 14.2-85
_ FULL-POWER PLANT TRIP l
- i' 6 (Startup Test) l Plant Condition or Prereouisites h
y Plant at normal steady-state full power condition with the electrical loads aligned for normal full power operation.
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g Test Objective
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To verify the ability of the primcry and secondary plant l
and the plant automatic control systems.to sustain a trip.
.yj from 100% powar and to bring the plant to a stable condition A
following the transient.
Test Summarv 1
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a
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, The plant will be brought to normal steady-state full power conditions with the electrical loads eligned for normal l'
full power opera tion.
The plant will be tripped by manual e
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tripjor by initiation of an automatic trip of the generator -
- - _ >' main breakers.
of fhe 0 ege, ape The parameters to be monitored will include nuclear flux; bre*p g reactor coolant loop temperature; pressurizer pressure and level; steam generator level, steam flow, and feed flow; n
turbine trip operation; reactor trip breaker operation; and controlling group rod position indication.
The parameters will be selected to determine the response of the plant control systems.
Acceptance Criteria The acceptance criteria that must be met to successfully complete the turbine test are:
the pressurizer safety valves shall not lif t; a.
b.
the steam generator safety valves shall not lift; c.
Safety Injection shall not be initiated; and, d.
no unacceptable water hammer in the steam cen-erators and/or f eedwa ter sys tem shall occur.
14.2-97