ML18043A728
| ML18043A728 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/07/1979 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906120172 | |
| Download: ML18043A728 (7) | |
Text
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consumers Power company General Offl~-:es: 212 \\Vi:,3t Michigan Avenue,.Jackson, Michigan 49201 ".A.rea Code 5i7 788*0550 June '!, 1979 Dj_rector, Huclear Reactor Regulation Att M:r Dennis L Ziemann, Chief Ope:::ating Reactors Branch No 2 US I~uclear.Regulatory Com.>nission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR FA!.iISADES PLAHT - 'l'ECP... NICAL S?:E:CIFICATIO:NS CHANGE RELATED TO PHYSICS TESTING Attached are three (3) origi~al and thirty-seven (37) conformed copies of a request fer a change to the Palisades Technical Specifications.
This chanze will provide for an improved physics testing program.
It also deletes portions of our Technical Specifications which are no longe:i:'
applicable.
It is requested that you complete your review o:f' thi? change by August l, 1979.
The rec;.u.ested change involves a single saf'c=ty issue.
Therefore, a. checi...in.
the e.Jllount of $4,ooo.oo is attached pursuant to 10 CFR 170.22, Class III change.
Da'lid P Hoffman Assistant Nuclear Licensing Administrator cc* JGKeppler, USNRC
'1906120112-
CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power Company on October 16, 1972 for the Palisades Plant be changed as described in Section I below:
I.
Change(s)
A.
In Section 1.1 under the definition of Low Power Physics Testing, change 1110-2% 11 to "2%."
B.
Add new Section 3.10.8 as follows:
"3.10,8 Center Control Rod Misalignment The requirements of Specifications 3.10.4.a, 3.10.4.c, 3.10.5 and S-5.1 may be suspended during the performance of physics te?ts to determine the isothermal temperature coefficient and power coefficient provided that only the center control rod is misaligned and the limits of Specification 3.10.3 are maintained."
C.
Delete Section 3.6.4.
D.
Delete Section 6.9.3,3,c~
II.
Discussion A.
The purpose of this change is to allow low power physics testing at flux levels high enough to minimize the influence of gannna background noise on the measurements.
The tests would be performed in the optimum range between the background level and the region of sensible heat, but no*greater than 2% thermal power.
The value of 2% is the upper bound for the Hot Standby condition, so the mode of operation during the tests would not-change. - The CE Standard Technical Specifications allow 5%
power for these tests.
B.
The purpose of this exception is to allow the use of only one control rod rather than an entire group during the performance of temperature and power coefficient tests.
In these tests, reactivity is inferred from the amount of control rod motion and, since the worth of a single control rod is about one quarter of that of a regulating group, the rod will travel four times as far.
A major source of uncertainty in these tests; that is, the measurement uncertainty in control rod positions over/small distances, will be thereby significantly reduced.
Using the center rod minimizes the impact on core power distribution and results in no azimuthal tilts. Margin to thermal limits will be maintained throughout the tests.
A similar specification (3/4.10.4) exists in the CE Standard Technic.al Specifications.
C.
This section was authorized on a one time only basis and has ~xpired.
D.
This section no.longer applies.
The report it.required has been sub-mitted.
III.
Conclusion(s)
Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board have reviewed these changes and find them acceptable.
CONSUMERS POWER COMPAJ.'IT Sworn and subscribed to before me this 7th day of June l979.
Thayer, Notar;;:;
Jackson County, Mic igan My commission expires July 9, 1979.
I
' I 2
1.1 REACTOR OPERATING CONDITIONS (Contd)
Low Power Physics Testing Testing performed under approved written procedures to determine *control rod worths and other core nuclear properties.
Reactor power during these tests shall not exceed 2% of rated power, not including decay heat and primary system temperature and pressure shall be in the range of 260°F to 538°F and 415 psia to 2150 psia, respectively.
Certain deviations from normal operating practice which are necessary to enable performing some of these tests are permitted in accordance with the specific provisions therefore in these Technical Specifications.
Shutdown Boron Concentrations Boron concentration sufficient to provide keff ~ 0.98 with all control rods in the core and the highest worth control rod fully withdrawn.
Refueling Boron Concentration Boron concentration of coolant at least 1720 ppm (corresponding to a shutdown margin of at least 5% ~P with all control rods withdrawn).
Quadrant Power Tilt The difference between nuclear power in any core quadrant and the average in all quadrants.
FA Assembly Radial Peaking Factor -
r The assembly radial peaking factor is the maximum ratio of individual fuel assembly power to core average assembly power integrated over the total core height, including tilt.
F T Total Radial Peaking Factor -
r The total radial peaking factor is the maximum product of the ratio of individual assembly power to core average assembly power times the local peaking factor for that assembly integrated over the total core height, including tilt. Local peaking factor is defined as the maximum ratio of the power in an individual fuel rod to assembly average rod power.
1.2 PROTECTIVE SYSTEMS Instrument Channels.
One of four independent measurement channels, complete with the sensors, sensor power supply units, amplifiers and bistable modules provided fdr
\\
each safety parameter.
Reactor Trip The de-energizing of the control rod drive mechanism (CRDM) magnetic clutch holding coils which releases the control rods and allows them to drop into the core.
1-2
3.6.4 DELETED 3-4oa
3.10 CONTROL ROD AND POWER DISTRIBUTION LIMITS (Contd) 3.10.6 Shutdown Rod Limits
- a.
All shutdown rods shall be withdrawn before any regulating rods are withdrawn.
- b.
The shutdown rods shall not be withdrawn until normal water level is established in the pressurizer.
- c.
The shutdown rods shall not be inserted below their exercise limit until all regulating rods are inserted.
3.10.7 Low Power Physics Testing Sections 3.10.1.a, 3.10.1.b, 3.10.2.b, 3.10.3.f, 3.10.4.b, 3.10.5 and 3.10.6 may be deviated from during low power physics testing and CRDM exercises if necessary to perform a test, but only for the time necessary to perform the test.
3.10.8 Center Control Rod Misalignment
- The requirements of Specifications 3.10.4.a, 3.10.4.c, 3.10.5 and s-5.1 may be suspended during the performance of physics tests to determine the iso-thermal temperature coefficient and power coefficient provided that only the center control rod is misaligned and the limits of Specification 3.10.3 are maintained.
Basis Suffrcient control rods shall be withdrawn at all times to assure that the reactivity decrease from a reactor trip provides adequate shutdown margin.
The available worth of withdrawn ro~s must include the reactivity defect of power and the failure of the withdrawn rod of highest worth to insert.
The requirement for a shutdown margin of 2.0% in reactivity with 4-pump opera-tion, and of 3.75% in reactivity with less than 4-pump operation, is con-sistent with the assumptions used in the analysis of accident conditions (including steam line break) as reported in XN-NF-77-18 and additional anal-ysis. ( 5 )
The change in insertion limit with reactor power shown on Figure 3-6 insures that the shutdown margin ~equirement for 4-pump operation is met at all power levels.
The 2.5-second drop time specif{et for the control rods is the drop time used in the transient analysis. 5 The maximum individual rod worth of inserted control rods and associated peaking factors have been used to demonstrate reactor safety for the unlikely event of a rod ejection accident as described in Reference 5.
The maximum worth of an inserted control rod will not exceed the values of the. specifi-cation for the regulating group insertion limits of Figure 3-6.
The limitation on linear heat generation rate ensures that in the event of a LOCA, the Nuclear Regulatory Commission criteria set forth in 10 CFR 50.45(b) will be met. (6 )
In addition, the limitation on linear heat rate ensures that the minimum DNBR will be mal.nta-ined. abo~e 1. 30 -ciliri.ng anticipated transients, and that fuel damage (if any) during Condition IV events such as locked 3-61
. ~ -.. '
6.9.3.3 Special Reports 6.10 6.10.1
- a.
Special reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable referenced specification:
Area Prestressing, Anchorage, Liner and Penetration Tests Primary System Surveillance
. Evaluation and Review Specification Reference 4.3 90 Days After Completion of the Test*
Five Years
- A test is considered to be complete after all associated mechanical, chemical, etc., tests have been completed.
- b.
Bimonthly status reports on the program to improve the reliability of the paths to prevent post-LOCA boron precipitation shall be submitted to the Division of Operating Reactors until completed.
- c.
Deleted.
RECORD RETENTION (Records not previously required to be retained shall be retained as required below commencing with the effective date of Technical Specification Change No. 20.
A -system for effic i.ent -record --retrieval*
shall be in effect not later than June 1976.)
The following records shall be retained for at least five years:
- a.
Records and logs of facility operation covering time interval at each power level.
- b.
Records and logs of principal maintenance activities, inspections, repair ~nd replacement of principal items of equipment related to nuclea:i;: safety.
- c.
Reportable occurrences.
- d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
6-26