ML20235N192
| ML20235N192 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/23/1989 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325B151 | List: |
| References | |
| NUDOCS 8903010093 | |
| Download: ML20235N192 (12) | |
Text
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[g NUCLEAR REGULATORY COMMISSION Q
WASHINGTON, D. C. 20555 Q.....]j INDIANA MICHIGAN POWER COMPANY DOCKET N0. 50-315-DONALD C. COOK AIUCLEAR PLANT, UNIT N0.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 121 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 9,1988, as revised January 10, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will cperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized
' by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common i
I defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part El of the Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated'in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
' Technical Specifications The Technical _ Specifications contained in Appendices A and.B.
as revised through Amendment No.121, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
{dc/re Qupy, A:ti g D'ir ' ['ld
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Project Dirbetorate 111-1 Di ision of Rea tor Projpc,s - III, IV, V Special(Pr jects U
Attachment:
i Changes to the Technical Specifications Date of Issuance: February 23, 1989 l
ATTACHMENT TO LICENSE AMENDMENT
' AMENDMENT NO.121 T0 FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages..The revised pages are identified by amendment number and contain marginal itnes indicating the area of change.
. REMOVE-INSERT 3/4 0 3/4 0-3 3/4 3-1 3/4 3-1 3/4 3-12 3/4 3-12 3/4 3 3/4 3-15 3/4 3-31 3/4 3-31 3/4 3-33 3/4 3-33 3/4 3-54 3/4.3-54 3/4 3-56 3/4 3-56 3/4'6-27 3/4 6-27 I
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3/4.0 APPLICABIE.ITY
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' SURVEILLANCE REQUIREMENTS f
i b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as folb>ws in these Technical Specifications:
ASME Boiler and Pressure Vessel Code and applicable Addenda Required frequencies for terminology for inservice performing inservice inspection inseeetion and testine criteria and testine activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above c.
required frequencies for performing inservice inspection and testing activities.
d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
Nothing in the ASME Boiler and Pressure Vessel Code shall be e.
construed to supersede the requirements of any Technical Specification.
4.0.6 By specific reference to this section, those surveillance which must be performed on or before July 31, 1987, and are designated as 18 month surveillance (or required as outage-related surveillance) may be delayed until the end of the Cycle 9-10 refueling outage (currently scheduled to begin during the second quarter of 1987). For these specific surveillance under this section, the specified tim,e intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance date during the Unit 1 19.67 refueling outage.
4.0.7 By specific reference to this specification, th6se surveillance which must be performed on or before April 1, 1989, may be delayed until the end of the Cycle 10-11 refueling outage (currently scheduled to begin during the latter part of the first quarter of i
1989.) For these specific surveillance under this section, the specified time intervals required by Specification 4.0.2 will be determined with the new initiation date established by the surveillance l
date during the Unit 1 1989 refueling outage.
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D. C. COOK UNIT 1 3/4 c.3 Amendment No, fff,121 I
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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION
~3.3.1.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERA 8LE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK. CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operatioris for the MODES and at the frequencies snown in Table 4.3-1.+
l
- 4. 3.1.1. 2 The logic for the interlocks shall be demonstrated OPERABLE orier to eacn reactor startup unless performed during the preceding 92 days.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation.
4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trio function shall be demonstrated to be within its limit at least once eer 18 months.
Each test shall include at least one logic train sucn that both logic trains are tested at least once per 36 months anc one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant enannels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
- The provisions of Specification 4.o.6 are applicable.
+
The provisions of Specification 4.0.7 are applicable.
l D. C. COOK-L* NIT 1 3/4 3-1 Amendment No. 100, 121
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y INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTA L1M1 TING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System-(E5FAS) instruments-tion channels and interlocks shown in Table 3.3 3 shall be OPERABLE with their. trip setpoints set consistent with the values shown in the Trip 5etpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
With an ESFAS instrumentation channel trip setpoint less c~onserva-a.
tive than the value shown in the Allowable Values column of Table 3.3 4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip <Setpoint value.
b.
With an ESFAS instrumentation channel inoperable, take the ACTION shown in Taele 3.3-3.
SURVEILLANCE REOUIREWENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall M demonstrated OPERARE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the modes and at the frequencies shown in Table 4.3-2. +
l 4.3. 2.1. 2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test. The total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by interlock operation. *
+ l 4. 3. 2.1. 3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is tne total number of redundant channels in a specific ESTAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.*
- The provisions of Specification 4.o.6 are applicable.
D. C. C00krovisions of Specification 4.0.7 are applicable.
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n INSTRUMENTOi]ON, POST-ACCIDENT INSTRUMENTATION LIl1111NG CONDITION FOR OPERATION 3.3.3.8 The post-accident monitorinn instrumentation channeP shown in Table 3.3-11 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
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With the number of OPERABLE post-accident monitorina channels less than required by Table 3.3-11, either restore the inoperable i
channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
The provisions of Specification 3.0:4 are not applicable.
9 SURVEILLANCE REQUIREMENTS 4.3.3.8 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CRANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7.*
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- The provisions of Specification 4.0.7 are applicable.
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.CONTA m m M T M st'RVEf t1ANcr REOUTRrwtNTS /concinuedi shall be consti:uzed of one baske: each from Radial Rows 1.
2, 4, 6. 8 and 9 (or from :he same row of an adjacen: bay if a basket frem a designated row cannot be obtained for weighing) vi:hin each bay.
If any basket is found to contain less chan 1220 pounds of ice, a representative sample of 20 additional baskets from the same bay shall be weighed.
The minimum average weight of ice from the 20 additional baskets and the discrepant baskst shall not be less than 1220 pounds /
baskee a: a 956 level of confidence.
The ice condenser shall also be subdivided into 3 groups of baskets, as follows:
Group 1 - bays 1 through 8. Group 2 -
bays 9 through 16, and Group 3 - bays 17 through 24 The minimum average ice weight of the sample baskets from Radial Rows 1. 2, 4, 6, 8 and 9 in each group shall not be less chan 1220 pounds /baske: 4: a 954 level of confidence.
The mini =um :otal ice condenser ice weigh: at a 954 level of confidence shall be calculated using all ice basket weights determined during this weighing program and shall not be less than 2,371,450 pounds.*
- l 3.
Verifying, by a visual inspec: ion of a: least two flow passages per ice condenser bay, that the accumuluien of frost or ice on flow passages between ice baskets, past lattice fra:es, through the in:ermedia:e and top deck floor grating, or past the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness of 3/8 inches.
If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representa:ive sample of 20 additional flow passages from :he same bay shall be visually inspected.
If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.
.. ore than one restricted flow passage per bay is w
evidence of abnor=al degrada:Lon of the ice condenser.*
At least once per ao mon:hs by lif:ing and visually inspecting tha e.
l accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verifying that :he ice baskets are free of detrimental strue: ural wear, cracks, corrosion or other damage.
The ice baske:s shall be raised at least 12 feet for this inspection.
The provisions of Specif1:a:Lon e.0.A are applicable.
The provisions of Specification 4.0.7 are applicable.
l D. C. COOK UNIT 1 De 6 27 Amendmen: No.70S,121