ML19225B408
| ML19225B408 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/15/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225B407 | List: |
| References | |
| SER-790615, NUDOCS 7907250118 | |
| Download: ML19225B408 (4) | |
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N UNITED STATES
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NUCLEAR REGULATGRY COMMISSION
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J W ASHINGTON, D. C. 20555 ha o
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 51 TO LICENSE NO. DPR-49 IOWA ELECTRIC LIGHT AND POWER COMPANY ~~
CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER 1.0 Introduction By letter dated December 27,1977 (IE-77-2317) Iowa Electric Light and Power Company (the licensee) requested a change to the Technical Specifications (Appendix A) appended to Facility Operating License
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No. DPR-49 for the Duane Arnold Energy Center (DAEC). The proposed amendment would change the Technical Specifications to:
(1) clarify 5
the requirements for permanent retention of certain records, (2) add two snubbers to the list of saubbers for the recirculation system in the drywell, and (3) bring a note associated with the table on control rod block instrumentation into agreement with the table.
2.0 Discussion ~
2.1 Quality Assurance and_Trainina Records One of the proposed changes is to clarify what quality assurance and training records must be retained onsite.
Section 6.10.2 of the DAEC Technical Specifications lists the " records which shall be retained for the duration of the Facility Operating License".
Section i-6.10.2.7 states that this shall include " records of training and f
qualification for members of the plant staff".
The licensee proposes to change this to read:
" Records of training and qualification for current members of the plant staff".
Section 6.10.2.9 states that the material to be retained shall include " Records of Quality As urance activities".
The licensee proposes to change this to rea6-
" Records of quality assurance activities required by the QA Manual".
417 278 7 9 o7 23 o ns
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' 2.2 Snubbers Sections 3.6.H and 4.6.H of the DAEC Technical Specifications list the limiting conditions for operation (LCOs) and surveillance requirements, respectively, for shock suppressors (snubbers).
Section 4.6.H.1 points out tFat " snubbers are categorized in two groups, ' accessible and inaccersible' based on their accessibility for inspection during reactre operation".
These two groups are inspected independently dCCording to a prescribed schedule.
Section 3.6.H 5 of the Technical Specifications authorizes the licensee to add (but not remove) snubbers without prior Comission approval.
Specifically, Section 3.6.H.5 states " Snubbers.may be added to safety related systems without i
prior license amendment to Tables 4.6-3 or 4.6-4 provided that a revision to Table 4.6-3 or 4.6-4 is included with the next license amendment".
In their submittal of December 27, 1977, the licensee proposed to revise Table 4.6-4, " Snubbers Inaccessible During Normal Operation" to add a secor.d snubber at two locations (specifically, at locations.SSA-10 and SSB-10) on the recirculation system in the drywell.
2.3 APRM Upscale (Not in Run Mode)
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Section 3.2.C of the DAEC Technical Specifications lists.the LC0 6
requirements for Control Rod Block Actuation.
The rod block logic circuits are energized whenever manual control rod movement is allowed.
Each logic circuit receives input trip signals from a number of trip j
channels and each logic circuit can provide a separate rod block signal to inhibit rod withdrawal.
In the event that an unsafe condition is being approached by the parameters being monitored, a trip of the permissive will occur and control rod movement will be prohibited or blocked.
The rod block circuitry is effective in preventing rod withdrawal, if required, during both normal (notch) withdrawal and continuous withdrawal.
The minimum instrument channels that must be operable in the control z
rod block system are listed in Table 3.2-C of the Technical Specifications.
Of the 10 parameters being monitored, Table 3.2-C specifies that a minimum of 2 o "APRM upscale (perable instrument channels must be available for the not in run mode)" trip system and that the trip level setting shall be "<12 indicated on scale" (i.e., equal to 'ar less than 12% of the 1593 MWt rated power).
There are 8 explanatory notes associated with the table.
A sentence in note 1 states:
"The SRM and IRM blocks need not be operable in 'Run' mode and the APRM and RBM rod blocks need not be operable in 'Startup' mode. While 3 cme of the 417 279
P.
APRM instruments do not need to.be operable in the startup mode (e.g.,
APRM Downscale), the sentence is not correct since Table 3.2-C requires the "APRM Upscale (Not in Run Mode)" instruments to be operable in the startup mode. To correct this, the licensee proposes to modify the sentence in Note 1 of Table 3.2-C to read:
"The 3RM and IRM blocks need not be operable in 'Run' mode and the APRM [except for ApRM Upscale (Not In Run Mode)] and RBM rod blocks need not La operable in 'Startup' mode".
3.0 Evaluation 3.1 Quality Assurance and Training Records The changes in wording in Sections 6.10.2.7 and 6.10.2.9 are to make the wording identical to that in NRC's, " Standard T hnical Specififica-tions for General Electric Boiling Water Reactors", NUREG-0123, Rev. I dated April 1, 1978.
The Standard Technical Specifications have been developed over the years in conjunction with the standard review plans and are those we recommend for all BWRs.
As noted above, the wording proposed by the licensee is iden ical to that in Section 6.10.2h and 6.10.2j u." the Standard Techt. ;al Specification. We conclude that the changes in wording in the requirements for retention of training i
and qualification and quality assurance records are acceptable.
3.2 Snubbers f
As discussed in 2.2 above, the licensee proposes to add "(2 ea.)" after snubbers SSA-10 and SSB-10 in Table 4.6-4 to indicate that there are now two snubbers with the same identification number installed at the subject location.
Thus, the table will now list 24 rather than 22 snubbers on the two recirculation loopt in the drywell and will bring i
Table 4.6-4 into conformance with the conditions in the facility. We conclude that the change to the table is acceptable.
I 3.3 APRM Upscale (Not in Run Mode)
As discussed in 2.3 above, the pu, pose of the proposed change is to bring note 1 in Table 3.2-C into agreement with the rsquirement in the I
Table.
Two of the APRM Upscale (Not in Run Mode) instrument channels must be operable in the startup mode as specified in the table with the trip setpoint equal to or less than 12 indicated on scale (i.e.,
<12% rated thermal power which for DAEC is 1593 MWt).
This setpoint T12%) is the same as that in Table 3.3.5-2, " Control Rod Withdrawal Block Instrumentaticn Setpointc" of the BWR Standard Technical 417 280
. Specifications, NUREG-0123.
The staff concludes that the requirement in Table 3.2-C of the DAEC Technical Specf fications is needed and is correct and that note 1 to this table should be modified to bring it into agreement with the table.
4.0 Environmental Considerations We have determined that this amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR Section 51.5(d)(4) that an environmental impact statement, negative declaration, or environmental impact appraisal need not be p epared in connection with the issuance of this amendment.
5.0 Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amtndment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission'-
regulations and the issuance of this amendment will not be inimical to the canmon defense and security or to the. health and safety of the public.
Dated: June 15,1979 417 28i
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