ML17325A644
| ML17325A644 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/03/1988 |
| From: | Miller H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Holahan G Office of Nuclear Reactor Regulation |
| References | |
| TAC-66016, TAC-66017, NUDOCS 8803080182 | |
| Download: ML17325A644 (10) | |
Text
NROS 19Se MEMORANDUM FOR:
G.
M. Holahan, Assistant Director for Regions III and V
Division of Reactor Projects III, IV, V and Special
- Projects, NRR FROM:
SUBJECT:
Hubert J. Miller, Director, Division of Reactor Safety, Region III LICENSING ACTION FOR D.
C.
COOK, LIQUID RADWASTE EFFLUENT LINE MONITOR (TAC NOS.
- 66016, 66017)
We have reviewed the Indiana and Michigan Electric Company's request for amendment of their Technical Specifications (TS) for D. C. Cook, Units 1 and 2, as requested in their letters to'NRC dated December 8, 1986, and August 7, 1987.
We find the proposed amendment acceptable and are providing you the enclosed Safety Evaluation and SALP assessment.
Eight staff hours were used for this evaluation.
Any questions on this matter should be directed to C F. Gill (FTS 388-5261).
.ORIGifvAL SlGNEO BIt.'UBEiiT, j. f~ilL-'=g
Enclosures:
1.
Safety Evaluation 2.
SALP Assessment 3.
Corrected TS pages cc w/enclosures:
D.
M. Crutchfield, NRR M. J. Virgillio, NRR J.
F. Stang, NRR E.
G. Greeman,'III B.L. Jorgensen, SRI Hubert J. Miller, Director Division of Reactor Safety RI I Iew RI r
P llips B
8803080182 880303 PDR ADOCK 050003i5 PDR ess RIII l.
,Wr ght M
1 er q'I
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPP R
ING AMEND EN S.
T F CILITY PER ING LI NS
'NOS.
DPR 58, DPR-74 INDIANA AND MICHIGAN ELECTRIC COMPANY D. C.
COOK NUCLEAR PLANT UNITS NO.
1 AND NO.
2 DOCKET NOS. 50-315, 50-316
1.0 INTRODUCTION
By letters dated December 8,
- 1986, and August 7,
- 1987, Indiana and Michigan Electric Company, the licensee, made application for amendment to Facility Operating License Nos.
C.
Cook Nuclear Plant, Units No.
1 and No. 2.
The proposed change concerned revisions to the Technical Specifications (TS) to replace the existing liquid radwaste effluent line monitor.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determ'ination and Opportunity for Hearing related to the requested action was published in the Federal Register on
(
FR
).
No requests for hearing and no public comments were received.
2.0 EVALUATION The licensee has proposed to change the monitor designation in TS Table 3.3-12, Item 1.a from 1-R-18 (2-R-18) to 12-RRS-1001 to reflect the new monitor.
Additional changes are proposed to:
( 1) allow the existing monitor to be used until the new monitor is operable, (2) indicate that operability of flowswitch RFS-1010 is required for operability of the new monitor, and (3) specify channel functional test surveillance requirements for the new monitor.
The reason for this request is to replace the existing liquid radwaste effluent line monitor, which has experienced continuing problems due to radioactive material buildup on the interior monitor surfaces and resultant background radiation interference which hinders the ability of the monitor to detect low radioactive discharge concentrations.
The new monitor is expected to be less susceptible to long-term radioactive material buildup and also more sensitive to the gamma component of the liquid radioactive effluent.
Both of these traits should improve performance of the new monitor over the existing monitor.
The staff's review of the above proposed change indicates that the proposal is acceptable and does not affect the reliability or operability of safety systems as required for safe plant operation, shutdown, or accident mitigation.
i The staff finds the above changes acceptable.
3.0.
ENVIRONMENTAL CONSIDERATION This amendment relates to an upgrading of liquid radioactive effluent monitoring capabilities for which there is no significant hazards consideration, there is no change in the types or increase in the amounts of any effluents that may be released offsite, and there is no significant increase in individual or cumulative occupational radiation exposure.
Accordingly, this amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
'.0.
CONCLUSION The staff 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 operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ACKNOWLEDGEMENT This evaluation was prepared by L. R. Greger and C.
F. Gill.
Dated:
ThSLK 3.3-12
, Minimum Channels Qmra~
- 1. Gross Radioactivity Monitors Providing Automatic Release Terminat'on
- a. Liquid Radwaste Effluent Line (12-RRS-1001) ht times of release 23 b.
Steam Generator Blowdown Line (1-R-19)
At times of release 24 c.
Steam Cenerator Blowdown Treatment Effluent (1-R-24)
At times of release 24
- 2. Cross Radioactivity Monitors Not Providing Automatic Release Ter.",.'na:
on
- a. Service Mater System Effluent Line (l-R-20, 1-R-28)
- 3. Continuous Composite Sampler Flow Monitor (l)per A" all times train
- a. Turbine Building Sump Effluent Line At all times 25
- 4. Flow Rate Measurement Devices
- a. Liquid Radwaste Line(RFI-285)
- b. Discharge Pipes*
c.
Steam Cenerator Blowdown Treatment Effluent (1-DFI-352)
At times of release At all times 16 XA At times of release 26
- Pump curves and valve settings may be utilized to estimate flow; in such
- cases, Action Statement 26 is not applicable.
+ Monitor 1-R-18 aay be used until 12-RRS-1001 is declared OPERABLE following initial installation.
+ OPERABILITY of 12-RRS-1001 includes OPERABILITY of flow switch RFS-1010, which is an attendant instrument as defined by Specification 1.6.
Do Co COOK ~ UNTT
TASLE i.3A NNION:T?VE LIQUID PR.UVT NNITORINQ INSTRUMENTATION SURVGLLANCK RKOUIRPlKN'S INrrRS.ENT..
QQ4$ E.
m~x SOURCE CilEW CSNNEL L!BRATION CHANNQ.
RJNCHONAL TES i 1.
Crass de+a or Qaaea Radf oactf vfty Nanf mrs pravfdfng a1arn and autaaatfc fsolatfon a.
Lfqufd Rahasta 0
Ktfluent Lfne (I2-RR~->oo>)
5.
Sthula Cenerator 0
41ee4ee KtfTuent Lfne c.
Steam Cene'or 0
dl~me Treatment KtRuent Lfhe 2.
Crass deta or Qnra Radf oactf vfty l4onft"rs Provfdfny Alarm dut Not Pravfdfng Aut~tfc Isolatfon a.
~ervfce Maar Sylph
~
~ luen.
Lfne 3.
Ccntfnuous Can"o!fte San@1 em a.
Turafne 8uf1df ng e~ K..luen Lfne N/A R(3)
R(3)
R(3)
R(3) 1(5) 0(<)
0(2) i.
Piaw Ra~ %nf~rs a.
Lfaufd Ra~su E..quent
- h. S~ Ceneratcr 310lKtM TreaC&t Lfne 0(4) 0(~)
N/A N/A N/A Qurfng Re1ea es Yfa Thfs Pa~v
TABLE 4.3-8 (Cont)
I ThBLE NOTATION (I)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the folloving conditions exists:
- 2 Alt3
~4 Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.*
Instrument indicates a dovnscale failure'.*
Instrument control not set in operating mode.*
(2)
The CHANNEL FWCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the folloving conditions exists:
l.
- 2
- 3
- 4.
Instrument indicates measured levels above the alarm setpoint.
Circuit failure.
Instrument indicates a dovnscale failure.
Instrument controls not set in operating mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using one or more sources vith traceability back to the National Bureau of Standards.
These sources shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHAhTEL CALIBRATION, sources that have been related to the initial calibration may be used.
(4)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch release are made.
(5)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the folloving conditions exists:
~2
~
- 3
~4,
- 5 Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.++*
Instrument indicates a dovnscale failure.+++
Instrument control not set in operating mode.*
Loss of sample flow.
Instrument indicates, but does not provide for automatic isolation.
hs equipment becomes operational.
- Instrument indicates, but does not necessarily cause automatic isolation; however, no credit is taken for automatic isolation on such occurrences.
D. C.
COOK - UNIT 1 s, ~
3/4 3-61 Amendment No.
In:~xrK Minimum Channels Qm;xal;>M
- 1. Gross Radioactivity Monitors Providing Automatic Release Terminat'on
- a. Liquid Radvaste Effluent Line (12-RRS-1001) b.
Steam Generator Blovdovn Line j2-R-14) ht times of release 23 At times of release 24 c.
Steam Generator Blovdovn Treatment Effluent (2-R-24)
At times of release 24
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Term:..a=:on
- a. Service dieter System Effluent Line (2-R-20, 2-R-28)
(1)per At all times train 25
- 3. Con"inuous Composite Sampler Flov Monitor
- a. Turbine Building S
"..p Effluent Line At all times 25 Flov Rate Measurement Devices
- a. Liquid Radvaste Line(RFI-285)
- b. Discharge Pipes*
c.
Steam Generator Blovdo~~
Treatment Effluent (2-DFI-352)
At times of release At all times At, times of release 26 XA 26
- Pump curves and valve set:ings may bc utilized to estimate flov; in such
.cases, Action Statemen-25 is not applicable.
+ Monitor 2-R-18 may be used until 12-RRS-1001 Is declared OPERABLE folloving initial installation.
Amendment No.
w OPERABILITY of 12-RRS-1001 includes OPERABILITY of flov svitch RFS-1010, vhich is an attendant instrument as defined by Specification 1.6.
D. C.
COOK - UN,IT'Q 3/4 3-54
T&te q 3 gglIalCTIPrK LIQUID PFMBlT.'tI iQRIHS t.fSHt~TATICt SuRVDL> 'SC=- R&:uI..-=-&TS IN1lRlMBPi QJLl)NEL C-:ECIC SCLRCE C~E:i(
t"44VlEL CALISROTICN C-~i"i>c FiP(C i iGN4.
i c37 1.
Crois Se& or~
Radfoactfvfty Mcnf-"rs provfdfny alarm and lute 4 c fso la fon Lfgufd Ra@as'w D
VRuoht Lfne (12-RRs-1001)
S.
Stem Generator 0
BlerCee Effluent Lfne c.
Steam Genera t-r D
BlMClrfl Tria~t Eff1uant Lfne 2.
Grass Se+ cr B~
.4dfcact'.v.J %nf-rs Pwvfdfng Alarn Bu Not Pwvfd'ng Aum !c Is~1atfon a.
Servfce Mater Sam
.. ivan Lfne 3e Cont! nuous ~osfta Sanplers
- a. 'urhfne Bufldfng
- -.. ident L'.ne R(3)
R(3)
R(3)
R(3)
Q(~)
Q(i)
Q(l)
Q(2) ri~ Ra& +cnf rs L:cu'a BC~su
~ 1vmt Sham h.ex~ r 8i~irh Tpma~t Lfni g(4)
D(~)
TABLE 4.3-8 (Cont)
I TABLE NOTATION (l)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 2
- 3
- 4 Instrument indicates measured levels above the alarm/trip se tpoint.
Circuit failure.*
Instrument indicates a downscale failure.*
Instrument*control not set in operating mode.*
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
l.
- 2
- 3
- 4 Instrument indicates measured levels above the alarm setpoint.
Circuit failure.
Instrument indicates a downscale failure.
Instrument controls not set in operating mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using one or more sources with traceability back to the National Bureau of Standards.
These sources shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent.
CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.
(4)
CHAhNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch release are made.
Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.~
Instrument indicates a downscale failure.++*
Instrument control not set in operating, mode.*
Loss of sample flow.
(5)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic 1
isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
I l.
I
~2
~
I
+43, I
- 4.
- 5.
I Instrument indicates, but does not, provide for automatic isolation.
As equipment becomes operational.
- ++
Instrument indicates, but does not necessarily cause automatic isolation; however, no credit is taken for automatic isolation on such occurrences, D. C.
COOK - UNIT 2 3/4 3-57 Amendment No.
Criteria SYSTEHATIC ASSESSMENT OF LICENSEE PERF01NANCE Cate or Ratin l.
Kana ement Involvement and Control in Assurin alit 2.
A roach to Resolution of Technical Issues From a afet Stand oint 3.
Res onsiveness to NRC Initiatives 4.
Enforcement Histor 5.
0 erational and Construction Events 6.
~Staffin (including Management)
Refer; to Part II, Table l, NRC Appendix 0516, for guidance
$ n deterlining appropriate categories.
EKHIBITI.l