ML20058L590
| ML20058L590 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/02/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L589 | List: |
| References | |
| NUDOCS 9008070310 | |
| Download: ML20058L590 (4) | |
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's,..... f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 42 TO FACILITY OPERATI4G LICENSE NO. NPF-62 CLINTON POWER STATION. UNIT NO. 1 ILLINDIS POWER COMPANY DOCKET NO. 50-461
1.0 INTRODUCTION
By letter dated February 5, 1988, the Illinois Power Comnany (IP), et al. (the licensees), requested an amendment to Facility Operating License No. !!PF-62 for the Clinton Power Station, Unit 1.
The proposed amendment would revise the Technical Specifications to incorporate the results of the Startup Test Program data.
2.0 EVALUATION At multiple locations in the Clinton Power Station (CPS) Technical Specifi~
cations (TS) preliminary values for trip setpoints or operating paramet.rs were inserted pending the actual specific values being determined during startup testing.
These preliminary values were so noted in the TS and the licensee committed to provide the appropriate values from the startup test program data within 90 days of the completion of the startup test program.
By this proposed amendment, the licensee has provided the parameters from the startup test program for incorporation into the TS.
Each of the changes is discussed individually below.-
l l
On page 3/4 3-21 item 2.d, the "**" is deleted from the trip setpoint and allow-able valus.
This is acceptable to the staff since the same values are retained that were originally found to be acceptable.
On page 3/4 3-22 item 4.a. the trip setpoint is changed from "<257.5" to "<110" and the allowable value is changed froc "<266" to "<118.5" and the "**" note is deleted from both values.
This is acceptable to the staff since the revised values represent the measured parameter and are more conservative than the original.
On page 3/4 3-23 item 4.1, the "**" is deleted from the trip setpoint and l
allowable value.
This is acceptable to the staff since the same values are retained that were originally found to be acceptable.
On page 3/4 3-24 item 5.e the "**" is deleted from the trip setpoint and allowable value.
This is acceptable to the staff since the same values are retained that were originally found to be acceptable.
9008070310 900802 PilR ADOCK 05000461 P
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Also on page 3/4 3-24, the "**" note at the bottom of the page is deleted entirely.
This is acceptable since the note is no longer referenced in the TS.
Changes proposed for pages 3/4 3-66 and 3/4 3-67 were withdrawn by the licensees I
during a telephone conversation on June 28, 1990.
Due to hardware changes that will be made during the second refueling outage beginning in October 1990, the values that were submitted would no longer be correct.
Therefore, the licensee r
will submit revised values following the sthetup testing after refueling No. 2.
The first change on page 3/4 4-2, to item a.1.f. replaces "33,000 gpm" with "31,341 gpm."
This revised figure representing the measured volumetric recir-culation loop flow that produces 100% core flow at 100% Thermal Power is within expected values and acceptable to the staff.
The second change on page 3/4 4-2, to item a.1.g. replaces "<50%** of rated loop flow" with "<30%** of rated loop flow." This change provides the measured loop flow at 30% thermal power that will sweep the cold water from the vessel bottom head preventing stratification.
This change is within the range of expected flows and provides an appropriate initiation for the surveillance.
The change is acceptable to the staff.
The next change on page 3/4 4-2, to items e and d, replaces "(39)#%" with "35.5W."
This figure represents the core flow with both recirculation pumps at rated speed and minimum control valve position.
This change is within expected values and is acceptable to the staff.
The last change to page 3/4 4-2 is to notes *, **, and #.
The changes to all three delete reference to the values being preliminary with final values to be determined during startup testing.
The portion of the notes that clarifies i
what the value represents is retained.
With the revision of the values, the portion of the notes that refers to final values to be determined is no longer needed, therefore this change is acceptable to the staff.
The first change on page 3/4 4-3, to item 4.4.1.1.3.c, replaces "33,000 gpm**"
with "31,341 gpm**."
This revised figure representing the measured volumetric recirculation loop flow that produces 100% core flow at 100% Thermal Power is within expected values and acceptable to the staff.
The next change on page 3/4 4-3, to item 4.4.1.1.3.d. replaces "(39)#%" with "35.5W."
This figure represents the core flow with both recirculation pui.pt at rated speed and minimum control valve position.
This change is within expected values and is acceptable to the rAr,'f.
The final change to page 3/4 4-3 is to note #.
The change deletes reference to the final value to be determined during startup testing.
The portion of the note that clarifies what the value represents is retained.
With the revision of the value, the portion of the note that refers to final values to be deter-l mined is no longer needed, therefore this change is acceptable to the staff.
1
3 On page 3/4 4-4 item 4.4.1.1.4 "50%*" is replaced with "30%*."
This change provides the measured loop flow at 30% thermal power which will sweep the cold water from the vessel bottom head preventing stratification. This change is within the range of expected flows and provides an appropriate initiation for the surveillance. The change is acceptable to the staff.
Also on page 3/4 4-4, the "*" note, which is still included with the revised value discussed previously, is revised to delete the reference to startup testina.
The note retains the description of the basis for the value and is acceptable to the staff.
On page 3/4 4-6 the "*" note is deleted from items 4.4.1.2.b.1,.2, and.3 and from the bottom of the page.
The note indicated that single recirculation flow control valve position-loop flow characteristics would be determined during the startup test program.
These have been determined and are included in this amendment.
Therefore, this reference is no longer needed and the deletion is acceptable.
On page 3/4 4-19 the "*" note is deleted from ACTION c.1 and from the bottom of the page.
The note indicated that condition I for action c was not applicable during the startup test program.
Since the program has been completed, that note is no longer necessary.
The deletion is acceptable.
On page B 3/4 4-1, in the second paragraph, the "( )" is deleted from around
"(30%)*" and "(50%)*" is replaced with "30%*."
These values represent the threshold thermal power and recirculation loop flow which will sweep the cold water from the vessel bottom head preventing stratification.
The values are within the expected range and are acceptable to the staff.
Finally, the portion of the "*" note at the bottom of page B 3/4 4-1 that refers to initial values with the final values to be determined during startup testing is deleted.
The measured values are included as part of this amendnient and the portion of the note that describes the basis for the values is retained.
Therefore, the change is acceptable.
In summary, the proposed changes to int.orporate the results of the startup test program in the TS have been reviewed by the NRC staff and found to be acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the instal-lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or a change to a surveillance requirement. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set i
4 forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no enviror. mental impact statement or environmental assessment need be prepared in conntction with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
John B. Hickman, NRR Dated: August 2, 1990
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