ML20147C287
| ML20147C287 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/09/1978 |
| From: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810120037 | |
| Download: ML20147C287 (8) | |
Text
,
6 GENER AL OFl4CU Nebraska Public Power District
" '" fet'c'd n CoSf'sHL"e"^ " "
October 9,1978 Director, Nuclear Reactor Regulation Attention: Mr. Thomas A. Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Proposed Changes to Radiological Technical Specifications Cooper Nuclear Station NRC Docket No.,50-298, DPR-46
Dear Mr. Ippolito:
In accordance with the provisions specified in 10CFR50.90, the Nebraska Public Power District requests that the Radiological Technical Specifications for Cooper Nuclear Station be revised to incorporate the following proposed changes.
Copies of the revised Technical Specification pages are attached with the changes marked.
1.
Tables 3.2. A (Page 1) and 4.2. A (Page 1).
Primary Con-tainment and Reactor Vessel Isolation The Temperature Indicating Switch (RWCU-TIS-99) should be deleted from these tables. The function of this instrument is to provide for process control rather than aid in providing primary containment isolation. As described in the Safety Analysis Report, Volume II, Section IV-9.3, the function of this switch is to isolate the filter demineralizer units upon high inlet temperature to prevent damage to the ion exchange resins.
Additionally, monthly testing of this instrument requires isolation of the RWCU system.
This results in thermal cycles on the system and the possibility of accel-1 crating stress corrosion problems.
t l
2.
Section 6.3.8.
Emergency Plan Drills l
I This change is submitted to resolve differences between the Technical Specification which specifies that Emergency Plan drills he conducted semi-annually, and Amendment O to the l
Cooper Nuclear Station Final Safety Analysis Report (Emergency Plan) and Regulatory Guide 1.101, Revision 1
)
which allow annual Emergency Plan drills. It is felt that one drill per year is sufficient to meet the recommendations of the Regulatory Guide 'and the intent of the FSAR.
Mh
'77r / dla #37 also
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< m Mr. Thomas.Ippolito October 9,1978 -
Page 2 3.
Figure 6.1.2.
Cooper Nuclear Station Organization Chart
' A letter dated July 26,- 1978 from G. L. Madsen (NRC) to NPPD reported the results of a routine inspection conducted at Cooper. Nuclear Station July 11-14, 1978. Section 5 of this report.noted that while Technical Specification Figure 6.1.2 indicates a Reliability Engineer assigned to the Station Superintendent's staff, the actual site organization included a
' Technical Assistant to the Station Superintendent.
Figure 6.1.2 is being revised to reflect the present station organization. One item revised on Figure 6.1.2 is the Station
~
Operators (unlicensed) from two per shift to three per shift.
., Technical Specification 6.1.3.F is also being revised to agree t
with the figure in this regard. _ Three unlicensed operators
- are presently required for a fire brigade in Technical Specification 6.1.3.G.
The safety significance of these proposed changes has been reviewed by appropriate District personnel, and under 10CFR Part 170, these changes are judged to be a Class II amendment.
Payment in the amount of $1,200 is enclosed with this submittal.
Should you have any questions or require additional information, please contact me.
In addition to three signed originals, 37 copies of the proposed changes are also submitted.
Sincerely yours, M
J.
. Pflant Director of Licensing.
and Quality Assurance JMP/jw:ars3/5 Attachments s
i.
r Mr. Thomas Ippolito 1
October 9,1978 Page 3 STATE OF NEBRASKA)
)ss PLATTE COUNTY
)
Jay M. Pflant, being first duly sworn, deposes and says that he is an authorized. representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to execute this request on behalf of Nebraska Public Power District; and that the statements in said application are true to the best of his knowledge and belief.
M Q y C PIhnt~
Subscribed in my presence and sworn to before me this kday of October 1978.
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N RY PUBLIC My Commission expires
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o COOPER NUCLEAR STATION TABLE 3.2.A (Page 1)
PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION INSTRUMENTATION Minimum Number Action Required When Instrument of Operable Components Component Operability -
Instrument I.D. No.
Setting Limit Per Trip System (1)~
is Not Assured (2 -
Main Stean Line High RMP-RM-251, A,B,C,&D
< 3 Times Full Power.
-2 A or B Rad.
Reactor Low Water Level NBI-LIS-101, A,B,C,6D
>+12.5" Indicated Level 2(4)
A or B Reactor low Low Water NBI-LIS-57 A & B
>-37" Indicated Level 2
A or B -
Level NBI-LIS-58 A & B Main Steam Line Leak MS-TS-121, A,B,C,&D
< 200 F 2(6)
.B' Detection 122, 123, 124, 143, 144, 145, 146, 147, 148, 149,
?
150 Main Steam Line High MS-dPIS-116 A,B,C,&D
< 140% of Rated 5:.eam 2(3)
.B Flow 117, 118, 119 Flow f
Main Steam Line Low MS-PS-134 A,B,C,&D
> 850 psig 2(5)
J Pressure i
High Drywell Pressure PC-PS-12, A,B,C,6D
< 2 psig 2(4)
A or B High Reactor Pressure RR-PS-128 A & B
< 75 psig i
D Main Condenser Low MS-PS-103 A,B,C,6D
> 7" Hg (7) 2' A cr B Vacuum I
Reactor Water Cleanup RWCU-dPIS-170 A & B
< 200%'of System Flow
.1 C
System High Flow
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4 1
4 COOPER NUCLEAR STATION TABLE 4.2. A (Page - 1)
PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION SYSTEM TEST AND CALIBRATION FREQUENCIES Instrument Item Item I.D. No.
Function Test Freq. Calibratica Freq.
Check Instrument Channels t
Reactor Low Water Level NBI-LIS-101, A,B,C,&D Once/ Month (1)
Once/3 Months Once/ Day Reactor Low Low Water Level NBI-LIS-57, A & B Once/ Month (1)
Once/3 Montlis
~ 0nce/ Day NBI-LIS-58, A & B i-Once/ Operating None Main Steam Line Leak MS-TE-121, A,B,C,6D Once/ Month (1)
Detection 122, 123, 124, 143, 144, Cycle-145, 146, 147, 148, 149, 150 io 1
Main Steam Line High Flow MS-dPIS-116, A,B,C,&D Once/ Month (1)
Once/3 Months None 117 Once/ Month (1)
Once/3 Months None 118 Once/ Month (1)
Once/3 Months None 119-Once/ Month (1)
Once/3 Months None Main Steam Line Law Press.
MS-PS-134, A,B,C,6D Once/ Month (1)
Once/3 Months None liigh Reactor Pressure RR-PS-128, A & B Once/ Month (1)
Once/3 Months None Condenser Low Vacuum MS-PS-103, A,B,C,6D Once/ Month (1)
Once/3 Months None Reactor Water C.U. High Flow RWCU-dPIS-170, A & B Once/ Month (1)
Once/3 Months None-Reactor Water C.U. liigh Space RWCU-TS-150 A-D, 151, 152, once/ Month (1)
Once/ Operating None Temp.
153, 154, 155, 156, 157, Cycle-158, 159, RWCU-TS-81 A,B,E,F, RWCU-TS-81 C,D,G,Il 4
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h 6.0 ADMINISTRATIVE CONTROLS 1
l 6.1 Organization f
I 6.1.1 The Station Superintendent shall have the over-all fulltime onsite responsibility for the safe operation of the Cooper Nuclear Station.
During periods when the Station Superintendent is unavailable, he i
may delegate his responsibility to the Assistant to Station Superintendent
{
or, in his absence, to one of the Department Supervisors.
6.1.2 The portion o'f the Nebraska Public Power District management which' relates to the operation of this station is shown in Figure 6.1.1.
1 6.1.3 The organization for ' conduct of operation of the station is shown in i
Fig. 6.1.2.
The shif t comp.ement at the station shall at all times I
meet the following requirements. Note: Higher grade licensed operators.
may take the place of lower grade licensed or unlicensed operators.
A.
A licensed senior reactor operator (SRO) shall be present at -
i the station at all times when there is any fuel in the reactor.
B.
A licensed reactor operator shall be in the control room at all times when there is any fuel in the reactor.
C.
Two licensed reactor operators shall be in the control room during all startup, shutdown and other periods involving signif-icant planned control rod manipulations. A licensed SRO shall either be La the Control Room or immediately available to the Control Room during such periods.
D.
A licensed senior reactor operator (SRO) with no other concur--
rent duties shall be directly in charge of any refueling opera-tion, or alteration of the reactor core.
A licensed reactor operator (RO) with no other concurrent duties shall be directly in charge of operations involving the handling of irradiated fuel other than refueling or reactor core alteration operations.
E.
An individual who has been trained and qualified in health physics techniques shall be on site at all times that fuel is on site.
F.
Minimum crew size during reactor operation shall consist of three licensed reactor operators (one of whom shall be licensed SRO) and three unlicensed operators. Minimum crew size during
\\
reactor cold shutdown conditions shall consist of two licensed reactor operators (one of whom shall be licensed SRO) and one unlicensed operator.
In the event that any member of a minimum shif t crew is absent or incapacitated due to illness or injury a qualified replace-ment shall be designated to report on-site within two hours.
G.
A fire brigade of ac least 3 members shall be maintained at all times.
This excludes the 3 members of the minimum shif t crew necessary for safe shutdowns, and other personnel required for other essentia". functions during a fire emergency.
-219-J
,o I
6.3 (cont ' d. )
6.3.5 In lieu of the "_ontrol device" or " alarm signal" required by Paragraph 20.203 (c) (2) of 10 CFR 20 each High Radiation Area (100 mrem /hr or f'
greater) shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by requiring notification and permission of the shift supervisor. Any individual or group of indi-viduals permitted to enter such areas shall be provided with a radiat1on j_
monitoring device which continuously indicates the radiation dose rate in the area.
6.3.6 All procedures described in 6.3.2, 6.3.3, & 6.3.4 above, and changes thereto, shall be reviewed by the Station Operations Review Committee and approved by the Station Superintendent prior to implementation, except as provided for in 6.3.7 below.
6.3.7 Temporary changes to procedures which do not change the intent of the original procedure may be made, provided such changes are approved by two members of the operating staff holding SRO licenses.
Such changes shall be documented and subsequently reviewed by the Station Superintendent i
within one month.
6.3.8 Drills of the Emergency Plan procedures shall be conducted annually, including a check of communications with offsite support groups. Drills on the procedures specified in 6.3.2.A, B, and C above shall be con-ducted as part of the retraining program.
REFERENCE 1.
SAR Subsection XIII-6.
226a
4 i
CNS ORGANIZATION CHART I
Station Superintendent Assistant to Station Operations Station Supenntendent Review Committee Techcral Assistant to Educational 4
Station Superintendent Specialist 1
?
Q. A. Supervisor Fire tection 1 1
I I
I Opera 3ons Supervisor Administrative s ry aM Nam Ma ntenance Supervisor Engineering Supervisor Physics Supervisor (SRO)
Supervisor I
I I
.I i
p I
I i
i i
w 9
Mechanical Foreman A instr. & Contrd Stuft Supervisors (SRO)
Reactor Engineers Electrical Foreman 1/S Mechanical Foreman B Supervisor Performance Engineer l
Electrical Engineer g
g g
instr. & Control Engmeer Mechanical Engineer 2/SI Unit Oper. (RO)
Engineenng Technicians Craft Personnet Electricians Instrument Techrucians 33 Station Oper.
(Unlicensed)
Health Physicist Chemist l
I Admsnistrative Contract Health Physics Chemistry Technicians Personnel Guards Technicians i
1/S one/ shift 2/S two/ shift 3'S three/ shift (10-NRC Reactor Operators License SRO-NRC Senior Reactor Operators License 1-Functional Position Only physically located in General Office Figure 6,1. 2
,e
. Cooper Nuclear Station
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Organization Chart f
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