ML17326B265
| ML17326B265 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/10/1986 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17326B266 | List: |
| References | |
| NUDOCS 8612220198 | |
| Download: ML17326B265 (19) | |
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UNITED STATES CLEAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 P
INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 f
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No. DPR-58 I.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for. amendment by Indiana and Michigan Electric Company (the licensee) dated January 27, 1986, 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 operate in confopnity 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 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 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications's 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:
8b122201'78 8b1210 PDR ADOCK 05000315 P
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specification changes are effective within 45 days of receipt of this amendment.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 10, 1986 Dave L. Wigginton, Project Manager PWR Project Directorate
$4 Division of PWR Licensing-A DPWRg WR-A DWigginton/mac 1)/ ~i/86 P
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l UNITE0 STATES I
NUCLEAR REGULATORY COMIVllSSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 86 License No.
DPR-74 1.
The Nuclear Regulatory CoIIIIission (the COIIIIission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated january 27, 1986, 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 operate 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 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 51 of the Commission's regulations and all applicable requirements have been satisfied.
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-74 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 86, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specification changes are effective within 45 days of receipt of this amendment.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 10, 1986 Dave L. Wigginton, Project Manager PWR Project Directorate 84 Division of PWR Licensing-A PWRg4DPWR-A Dlgigginton/mac 1$/g /86 P t 4
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ATTACHh>ENT TO LICENSE AflENDhfENTS AhiENDNENT NO. 99 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDhiENT NO. 86 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS. 50-315 AND 50-316 Revise Appendix A as follows:
Remove Pa es Unit 1
3/4 3-5 3/4 3-8 3/4 3-12 3/4 3-13 3/4 3-14 Unit 2 3/4 3-4 3/4 3-7 3/4 3-11 3/4 3-12 3/4 3-13 Insert Pa es 3/4 3-5 3/4 3-8 3/4 3-12 3/4 3-13 3/4 3-14 3/4 3-4 3/4 3-7 3/4 3-11 3/4 3-12 3/4 3-13
TABLE 3. 3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION n
FUNCTIONAL UNIT TOTAL tP.
OF CHANNELS MINIMUM CHANNFLS CHANNELS APPLICABLE TO TRIP OPERABLE MOOES ACTION 20.
Reactor Coolant Puap Breaker Position Trip A.
Above P-8 B.
Above P-7 and Below P-8 21.
Reactor Trip Breakers 1/breaker 1/breaker 1
.2 1/breaker 1/breaker per oper-ating loop 1,
2 3*
4*
5*
10ll 1, 13, 14 22., Automatic Trip Logic 1,
2 3*
4*
5*
1, 14 CrJ I
CPl
TABLE 3.3-1 Continued ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT STAHOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />;
- however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification
- 4. 3.1.1.1.
ACTION 10 - With one channel inoperable, restore the inoperable charnel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to below P-8 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Operation below P-8 may continue pursuant to ACTION 11.
ACT ION ll - With less than the Minimum Number of Channels
- OPERABLE, operation may continue provided the inoperable ch:nnel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 12 - With the number of channels OPERABl.E one less than required by the Hinimvm Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STAHOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the reactor trip breakers.
ACTION 13 - Kith one of the diverse trip features (Undervoltage or shurt trip attaclz:ent) inoperable, restore it to OPERABLE status with'n 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or declare the breaker inoperable and apply A.ION l..he breaker shall not be bypassed while one of the diverse tr'p features is inoperable except'or the time recuired for per orming maintenance
+o restore the breaker to OPERABLE status.
~, I
ACTION 14 - With the nu~ber of OPERABLE channels one less than the Minimum
~ 'hannels OPERABLE requirement, restore the inoperable channel to OPEARABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the reactor trip breakers within the next hour.
DES IGHATIOH REACTOR TRIP SYSTEM INTERLOCKS CONOITION ANO SETPOIHT FUNCTION P-6 With 2 of 2 Intermediate Range 11 P-6 prevents or de=eats Neutron Flux Channels 6 x 10 t'h e manUal bloc.'< of amps.
source range reac:or trlp.
0.
C.
COOK - UNIT 1 3/4 3-8 Amendment No. 99
REACTOR TRIP SYSTIH IHSTRIIHPNTATIOH SVRVEII.LANCE RE VIREHI'.tlTS FUIICTIOHAL UIIIT CIIAHHEfe CIIECK CIIAHHCL CALIBRATIOH CIIANHEL FUNCTIOHAL TEST HODES IH MIIICII SURVI;I LLAtICE RE VIREO Hanual Reactor Trip h.
Shunt Trip Function B.
Under vol t age Trlp Function 2.
Pover Range.
Neutron Flux N.h.
N.A, H.A.
N.A.
D (2)
~ H(3) and Q(6)
S/U(1)(10) 1, 2, 3*, 4*, 5*
S/U.(1)(10) 1, 2, 3*
4*
5*
1, 2aftd*
3.
Pover Range.
Heutron Flux, lllgh Positive Rate N.h.
R (6) 2 4.
PoMer Range, Neutron Flux, lllgh Negative Rate H ah.
(6) lg 2
5.
Intermediate
- Range, Neutron Flux R(6)
S/II ( I )
2 and
~
6.
Source
- Range, Heutron Flux R(6)
H and S/III1) 2(7)
~ 3(7)
~
4 7.
Ovcrternpcrature g T 8.
OverpoMer h T 9.
Pressurizer Pressure--I'M 10.
Pressurizer Prcssure--lllgh H
H 1,
2 1,
2 1,
2 1 ~
2 11.
Pressurizer Mater Level--lligh 12.
lass of I IoM - Sin<tie i@op I,
2
1'AIII.E 4. 3-l (Contlnne<l)
REnCTOR TRIP SYSTEH INSTRUHFNTATInN SURVEII.I.ANCF. RE UIRFHFNTS g
FUlICTIONAL UNIT
- CIIANNRI, CIIECK CIIANNEL CALIllRATION CIIANNEL FUNCTIONAL TEST HOOFS IH Wlrclt SllRVEILLANCE RF. Nil<El) 13 ~
Loss of Floe - Two I~ps H.A.
1i.
Steam Generator Mater Level-Lov-Lov 1,
2 Steam/Feedvater Floe Mismatch and Lov Steam Generator Hater Level 1,
2 16.
Undervoltage - Reactor Coolant Pumps N.h.
17.
Underfrequency - Reactor Coolant Pumps H.h.
18.
Turbine Trip h.
Lo~ Fluid Oll Pressure B.
Turbine Stop Valve Closure N.A~
N.A.-
N. h.
H.h S/U {1) 5/U t I )
1, 2
1, 2
o)
KC Oc 22.
Reactor Coolant Pump Breaker Position Trip Reactor Trip Breaker h.
Shunt Trip Function O.
Undervoltage Trip Function Automatic Trip logic 23.
Reactor Trip Bylines Breaker 19.
Safety Injection Input from ESF N.h.
H.A, N.AD N.h.
H.h.
N.A.
H,h, N.ho H.h.
N.A.
N.h.
Ht4)
M(5)( I I) aI1d S/U( I)( I I)
M(5)( I I) and S/U(1)( I I)
M(5)
M(I2) and S/U(l)(l3) 1, 2
N.h.
l,2,%,4*,P 3A 4*
5A l,2,>,4*,P l,2,>,4*,W
I
TABLE 4.3-1 Continued
}!QjDT }g (') (2) (3) With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. If not performed in previous 7 days. Meat balance only, above 15."of RATED THERlQL P01"ER. hd5ust channel if absolute deaf ference > 2 percent. Compare incore to excore axial imbalance above 15'f RATED THERMAL POWER. Recalibrate if absolute difference ~ 3 percent. (4) Yznual ESF functional input check every 18 months. (5) Each train teste'd every other month. (6) (7) Neutron detectors may be excluded from CHANNEL CALIBRATION. Belo~ P-6 (BLOCK OF SOURCE RANGE REACTOR TRIP) setpoint. (8) (Reserved) (~) (Reserved) (10) The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of.the undervoltage and shunt trip circuits for. the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit(s). The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers. (12) Loca1 manual shunt trip prior to placing breaker in service. (13) Automatic Undervol tage Trip. D-C. COOK-UNIT 1 3/4 3-14
- wendc}ent 8+
99
A 0 0
- 16. Undervoltage-Reactor Coolant Pumps c
- 17. Underirequency-Reactor Coolant Pumps
- 18. Turbine Trip TOTAL NO.
4 1/bus 4-1/bus CHANNELS Xo 'K~I NININJM CHANNELS QPER~BL APPLICABLE ODES ~C~O O
- h. Lov Pluid Oil Pressure B. Turbine Stop Valve Closure
- 19. Sal.'ety In)ection Input from ESP
- 20. Reactor Coolant Pump Breaker Position Trip A Above P-8 I
B. Above P-7 and below P-&
- 21. Reactor Trip Breakers
- 22. Automatic Trip.Logic 1/breaker 1/breaker 1/breaker 1/breaker per operat-ing loop 1~
2 2 3* 4* 5* 1, 2, 3*, 4*, 5* 70 60 10 11 l, 13,14
~t ~ ued ACT=ON 10 - Pith onc channel inoperable, restore the inoperablc channel to OPERABLE statu" vithin 2 hours or reduce THE."-'rAL PO'4ck to below P-8 virhin the next 2 hours. Operarion below P-8 may continue pursuant to ACTION 11. ACT.ON 11 - arith less than the Minimum Number of Channels OPERABI"., operation may continue provioed the i,noperable channel is placed in the tripped condition vithin 1 hour. AC ION 12 - Pith thc number of ihannels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, rcstozc the inope able channel to OPERABLE status vithin 48 hours or be in HOT ST~XDBY ~ vithin the next 6 hours and/or open the reactor 'trip breakers. ACTION 13 - hith ore of the diverse trip features (Undervoltaae or shunt tr'p at:achment) inoperable, restore it to GPEPABLE status with n 4S hours or declare the breaker iroperable and apply ACTION l..he breaker shall not Le bypassed while one of the diverse tr'p =eatures 's incperable except for the tir..e recu'red for per=c."'.".g -...ainte. arce +o restore the breaker to GPE."-ALE status. ACTION 14 - With the number'f OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPEARABLE status within 48 hours or open the reactor trip breakers within the next hour. ~ ~ ~ p-6 Pith 2 of 2 Intermediate Range 11 P 6 prevents or defeats Neutron Flux Channels < 6 x 10 the manual block of amp 5 ~ source range reactor trip. D. C. COOK - VNIT 2 3/4 3-7 AMENDM rT No. 86
I~~ILILIL" A 3 9 l. Manual Reactor Trip A. Shunt Trip Function B. Undervoltnge Trip Function 2. Pover Range, Neutron Flux 3. Pover Range, Neutron Flux/ High Positive Rate 4. Pover Range, Neutron Flux, .High Negative Rate 5. Intermediate
- Range, Neutron Flux 6.
Source
- Range, Neutron Flux CHANNEL
~CRUX N.A. N.Ao N.Ao '.A. CHANNEL ~C~IlRAT/OH N.A.. N.A. D(2,8),M(3 ~ 8) and Q(6,8) R(6) R(6) R(6,8) R(6,8) CHANNEL FUNCTIONAL sou(i) (io) S/U(>) (lo) M and S/U(l) S/U(1) M(8) and S/U(l) MODES IN NlICH SURVEILLANCE ~E~tJ gEQ 3* 4* 3* 4* 5* 1, 2and* li 2 1, 2 1, 2 and ~ 2(7), 3(7)~ and 5 ~ O 7. Overtemperature 4T 8 ~ 9 ~ Overpower 4T IPressurizer Pressure Low
- 10. Pressurizer Pressure High ll. Pressurizer Water Level High S
12. Loss ot Floe Single Loop S R(9) R(9) R(8) 1, 2 1, 2 1, 2 1, 2 l~ 2
1'KIII.K 4,3-! (Cont Inuadl REACTOR TIIIP SYS'TEII ItISTRIIHFttTATIAtlSURVEII.I.ANCE RE UIREHEHTS C M FUHCTIOHAL UttIT CIIANHF.IK CIIKCK CIIANNEI CALII I RATION CIIANNEL FUNCTIONAL TEST HnnF.S IN mlICII SIIRVEILLANCK R III IcEI) 13 ~ Loss of Floe - TMcc I~ps H.h 14. Steam Genertttor Mater Level 2 15. Steam/Fecdvater FloM Hlsmatch and S Locc Steam Generatnr Mater I~vol 1 ~ 2 16. Undervoltage - Reactor Cnolant Pumps H.A. 17. Uctdertrecluency - Reactcir Coolant Pumps N.h. 18. Turbine Trip h. Lac Fluid Oil I'ressure 8 ~ Turbine Stop Valve Closure H.h. N.h N.h. N.A. S/U t 1) S/U II ) I ~ 2 2 19. Safety Injection Input frcim ESF N. h. H.A. H(4) 1 ~ 2 II. Undervol tage Trip I'unction 20'eactor Coolant Pump Breaker Position Trip 21'eactor Trip Breaker g'. Shunt Trip Function 0 22 ~ Automat,ic Trip I~glc CO 23. Reactor Trip Bypass Breaker N.h. H.h. tt.A. N.h. N.A. N.h. N.A. N.A. N.h. N.A. N.h. >>(5) M( l2) and S/U(1)( l3) I 2 3k 4* 5A l,2,>,4*,N M(5)(lI) and S/U(l)(lI) I, 2, 3 4*. 5" M(5)(ll) and S/U(l)(ll) I, 2, 3" '4*
a i' n 4"used KZ~N 4ith the reactor trip system breakers closed and the control roc drive system capable of rod vithdraval. (1} If not performed in previous 7 days. (2) (3) (4) (5) Heat balance only. above 15l of RATED THERMO. POVER. Adjust channel if absolute difference > 2 percent. Compare incore to excore axial offset above 15% of RATED THELI<L Pohcy. Recalibrate if absolute difference p 3 percent. . Manual ESF functional input check every 18 months'. Each train tested every other month. (6) Neutron detectors may be excluded from CKQiHEL CALIBRATION. (7) Below P-6 (BLOCK OF SOURCE RANCE REACTOR TRIP) setpoint. The provisions of Specification 4.0.4 are,not appli,cable. The provisions of Specification 4.0.4 are not applicable for fl(41) and f2(t51) penalties. (See also note l of Table 2.2-1) The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuits(s). The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers. (12) Local manual shunt trip prior to placing breaker in service. (13) Automatic Undervoltage Trip. D. C. COOK - UNIT 2 3/4 3-13 AHEND~ NO. 86}}