ML20199L071
| ML20199L071 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/24/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199L032 | List: |
| References | |
| NUDOCS 9712010269 | |
| Download: ML20199L071 (4) | |
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UNITED S'.'ATES
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<i NUCLEAR REGUL ATORY COMMISSION
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WASHINGTON D.C. 30666 0001 SAFETY EVAt0AT10N BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.182 TO FACILITY OPERATING llCENSE NO. DPR-40
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OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION. UNIT NO. 1 DOCKET NO. 50-285 1.0 INTRODtiCTION
- 20. 1996. Omaha Public Power District (OPPD)
By_ application dated May requested changes to the Technical Specifications (Appendix A to FacilityThe Operatirg License No. DPR-40) for the Fort Calhoun Station. Unit No. 1.
requested changes would clarify surveillance test (ST) requirements found in TS 3.1. Tables 3-1, 3-2. 3-3, and 3 3A.
In addition, several TS discrepancies would be corrected or clarified.
2.0 EVALUATION The changes to the Table of Contents are administrative in nature to reflect the removal of incore instrumentation (Specification 2.10.3) from the TS by Amendment 167. This is acceptable to the staff.
The change te Specification 2.1.7(1)b is proposed to delete the requirement that tests the alarm signal monthly per Specification 3.1. Table 3-3. Item 6.
The test that verifies the high and low pressurizer level alarm settings and the pressurizer heater cutout function is unnecessary.
Operating experience has shown that a shiftily pressurizer level verification as proposed in Specification 3.1. Table 3-3. Item 6.a is sufficient to detect any level deviation and verify that operation is within safety analyses assumptions.
The level alarms serve as early warning devices but do not provide an accident Replacing the monthly test with a monthly channel check mitigeion function.
to verify instrument operability is in accordance with NUREG-1432. Combustion Engineering (CE). Standard Technical Specifications (STS). SurveillanceThe Requirement (SR) 3.3.11.1 (post accident monitoring instrumentation).This monthly channel check sup)lements the shiftily level verification.
change is acceptable to t1e staff.
The Bases of Specification 3.1 is being revised to clarify expectat' ions regarding a channel check of channels that are normally off scale when the surveillance is required.
In this situation, the channel check only verifies that they are off scale in the same direction. Off scale low current loop M $ss PDR
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ChMnels will be verified to be reading at the botttet of the range and not failed do.<nscale.
These statements are taken from the Cases of CE STS SR 3.3.4.1 Engineered Safety Features Actuation System (ESFAS) Instrumentation (Analog) and are acceptable to the staff.
2 In addition, the Bases of Specification 3.1 is being revised to clarify that power operated relief valve (PORV) actuatior is not required during the channel functional test of the PORV low temperature setpoint (Table 3 3, item i
18.a).
PORV actuativa is not appropriate because it could result in an
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undesirable depressurization of the reactor coolant system at power.
This clarification is modeled after a similar statement from the Bases of SR 3.4.12.6 (Low Temperature Overpressure Protection (L10P) System) of the CE STE and is acceptable to the staff.
Changing Specification 3.1. Tables 3 1, 3 2, 3 3, and 3 3A by using defined terms to enable the Surveillance Method to match the Surveillance function is an administrative change designed to sim)lify the tables.
Removal of the extraneous monthly test does not alter t1e surveillance requirement because the newly added terms ure equivalent in meaning to the deleted text and ensure that proper surveillance testing 1s performed.
The reordering of several items in tLe tables into a Check-Test-Calibr_te sequence adds consistency to the tables.
Text revisions in the Channel N scription and Surveillance t
function columns of Table 3 1 and 3 2 add clarity and consistency.
Footnote No.. in Table 3-1 concerning the bistable trip tester was deleted Decause it is redundant and, therefore, unnecessary.
These changes are consistent with the CE STS and are, therefore, acceptable.
The Surveillance function of Table 3 1, item 1.c (Power Range Safety Channels) is being changed to " Test" from " Calibration and Test" because it is not necessary for item 1.c to recuire both since item 1.b already requires the power range safety channel acjustment (calibration) to be performed daily. As stated in the Bases of Specification 3.1, "The minimum calibration frequencies of once-rer day for the power range safety channels... are considered adequate." For further clarification, the Bases of Specification 3.1 is revied to note that the daily calibration is a heat Jalance adjustment only.
These changes are acceptable to the staff.
Chang';g Table 3-1, item 4 (Thermal Margin / Low Pressure (TM/LP)) to use the defined term CHANNEL CAllBRATION will allow the licensee to modify the current IM/LP calibration recuirements with no impact on safety.
Calibration of the i
temperature input anc pressure input will still require calibration to known standards (i.e., resistance and pressure). but will allow the calibrations to be done separately instead of coincidentally. The channel functional test that follows the cha*)nel calibration verifies proper function of the TM/LP circuitry. The change to item 4 is acceptable to the staff.
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Thehrbposaltoremovetheword" Instruments"fromtheChannelDescriptlonof Tabl 2, item 14 makes the Channel Description consistent with the Surveillance Method. Table 3 2, item 14 is not intended to verify safety injection tank (SIT) instrumentation operability but rather that the SIT level and pressure measurements are within limits.
This change follows the
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3-conclusion of deneric Letter (GL) 93 05. Item 7.4. "Line-Item Technical Specifications improvements to Reduce Surveillance Requirements for Testing During Power Operation." that states that the surveillance should only confirm that the parameters defining SIT operability are within their specified limits. As a result, this change is acceptable to the staff.
Items 22 and 24 are added to Table 3 2 to clearly state the reguirement for testing manual actuation of the engineered safety features (ESF) channels for off-site power low signal (OPLS) anti auxiliary feedwater.
Although testing the manual actuation of these channels is done via the existing technical specifications, the requirement to do so is not clearly stated.
Reordering j
Table 3 2. Item 23 into a Check-Test Calibrate Surveillance Frequency sequence adds clarity and consistency. The addition of Footnote No. 7 to Table 3 2 clarifies that the refueling frequency ESF channel functional test pertains to the backup channels such as derived circuits and equipment that cannot be tested when the plant is at power.
These clarifications are acceptable to the staff.
The revisions to Table 3-3. Item 6 which reorders the Check Test-Calibrate Surveillance Function sequence is an administrative change and is consistent with CE STS SR 3.4.9.1 (Pressurizer Water Level).
Reordering Item 6 into a Check Test Calibrate Surveillance Function sequence makes item 6 consistent with the ordering of the other items in Table 3 3 and is accept:51e to the staff.
Table 3 3. Item 21. PORV Operation Acoustic Position Indication Channel and item 23. Safety Valve Acoustic Position Indication Channel are being revised to a channel functional test from a channel / circuit check.
An oscillator and installed impac+ ors are used to generate noise signals when testing these channels, and, therefore, this surveillance is more accurately described as a channel functional test rather than a channel check.
Items 21 and 22. PORV Block Valve Operation & Position Indication, are being revised to delete the requirement to verify operation of the emergency >ower supply.
Permanent Class 1E emergency power supplins the PORV and PORV Block valve.
Therefore, verification of PORV or PORV block valve operability while powered from the emergency power supply system is unnecessary. The prcposed revision is in accordance with the exception for plants with a permanent Class 1E power supply that provides power to theso valves as stated in CE STS SR 3.4.11.4 and is, therefore, accestable.
Based on review of the proposed changes to the Fort Calhoun Unit 1 TS as discussed above, the staff concludes that the proposed TS changes clarify and standardize existing surveillance requirements, remove redundant requirements.
correct minor oversights from previous ank 3dment requests, and are in accordance with NUREG 1432. CE STS and thccefore, are acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission s regulations, the Nebraska State official was notified of the proposed issuance of the amendment.
The State official had no comments, i
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility co.nponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC 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 the amendment involves no significant hazards consideration, and there has been no public cor.nent on such finaing (61 FR 44361). Accordingly, the amendment meets the eliaibility Criteria for categoricalexclusionsetforthin10CFR51.22(c)(9).
Pursuantto10CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission 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 ope"ation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety o' the public Principal Contributor:
S. Rhow Date:
November 24, 1997