ML20235K875
| ML20235K875 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/14/1989 |
| From: | Milano P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235K870 | List: |
| References | |
| NUDOCS 8902270283 | |
| Download: ML20235K875 (11) | |
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.g NUCLEAR REGULATORY COMMlSSION i
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FORT CALHOUN STATION, UNIT NO. 1 gENDMENTTOTACILITYOPERATINGLICENSE Amendment No.119
' License No. OPR-40 l
1.
The Nuchar Regulatory Comtr.ission (the Ccmission) has found that:
A.
The. application for amendment by the Omaha Public Power District (the licensee) dated Decelnber 16, 1988, complies with the standards-and requirements of the Atomic Energy Act of 1954, as amended (the A(.t), and ths Comission's rules and regulations set forth in 10 CFR Chapter I; E.
The facility will operate in conforaity with the application, as
. amended, the provisions of the Act, and the rules and regulations of the Commission; C.
Yliere is reasonable assurance:
(i)thattheactivitiesauthorized by this an.endinent can be conducted without endangering the health and safety of the pt;c N, and (11) that such activities will be conducted in con.plianwe with ths Cons.ission's regulations; D.
The issuance of this license amendment will not be iniurical to the coumon'.clefense and security or to the health and safety of the public; o
and E.
The issuance of this arnendment is in accordance with 10 CfR Part 51 of the Corr. mission's regulations'and all applicaDie requirements have been satisfied.
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Accordhgly, Facility Operating License No. DPR-40 is anended by charges to the Technical Specifications as indicated in the attachment to this
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license amendn.ent, and paragtaph 3.5. of Faci 1*ty Operating License No.
OPR-40 is.hereby amended to read as follows:
1 B.
Technical Specifications 1
The Technical Specifications contained in Ar/pendix A, as revised through Amendment No.119, are hereby incorporated in the license. The licensee shall operate the facility in t.ccorcance with the Technical Specific 6tions.
3.
Facility Operating Literse Nc. DPR-40 is hereby amended in that paragraph 3.0 has been deletsd.
4 The license amendment is effective as of its date of issunnte and fully l
implemented with 30 days of the date of issuance.
FOR THE NUCLEM REGULAT0CY C0f'PISSION LALu.5 %
.f4 Jose A. Calvo, D! rector Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects
' Office of Nuclear Reactor Regulation Attachmer.t :
Changes to the Teernical Specifications Date of Issuance:
February 14, 1989
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-ATTACHMENT T0. LICENSE AMENDFENT NO. 119 i
FACILjTYOPERATINGLICENSENO.DPR-40 DOCKETN0.iS0-289 Revise Appendix "A" Technical Specifications as indicated below. The reyised:
pages are identified by amendment number and contain vertical lines' indicating the area of change.
Remove Pages Insert Panes 2-2a 2-2a 2-9 2-9 2 20 2-20 3-46 3-46 5-1 5-1 5-L' 5-5 5-8 5-8 5-12 5-12
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.. ' " 270- LIMITINGCON0lTIONSFOROPERATION-2.1< Reactor Coolant 3ystem (. Continued)
F 2.1,1. Operable Components-(Continued)
,(b)l When the water level above the top of the irradiated fuel assemblies seated within the reactor'versel is i
less than.1E feet, both. shutdown cooling heat ex-l changers and at least two LPSI or containment spray pumps shall be operable l
f beeptions-All decay heat reinoval loops may be mcde inoperable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided (1) no operations'are permitted that would cause dilution of the reactor Coolant system boron concentration,'(2) no refueling operations are takir.g place,'and (3) all containment penetrations providing direct access from the containment atmosphere to the
.l outside atmosphere are closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(5) At least one reactor coolant pump or one low pressure:
l' safety injection pump in the shutdown cooling mode shall be in cperation whenever a change is being made in the boron concentration of the reactor coolant when fiuel is in
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the reactor.
(5) Both steam generators shall be filled above the low steam generator. water level trip set point and available to rerove decay heat whenever the average temperature of th
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rea: tor coolant is above 300 F.
Each steam generator shall be demonstrated operable by: performance of th? in-service inspection program specified in Section 3.li
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prior to exceeding a reactor coolant temperature of'300 F.
(7) Maximum reactcr coolant system hydrostatic test pressure shall be 3125 psia.
A maxi;num of 10 cycles of 3125 psia i
hydrostatic tests are allowed.
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(8) Reactor coolant system leak and hydrostatic test shall be conducted within the limitations of Figures 2-1A and 2-18.
(9) Maxitum secondary hydrostatic test pressure shalil not exceed 1250 psia. A mi'nimum measured temperature of 73*F is required.
Only 1.0 cycles are permitted.
H (10) Maximum steam generator steam side leak test pressure shfil not exceed 1000 psia.
A minimum measured temper-aturc of 73*F is required.
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l (11) A non-operating reactor coolant pump shall not be started j
unless at least one of the following conditions is met.
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1 2-2a Amendment No. 39,66,66,7Z,119 I
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i 2'O ; LIMITING COND?TIONS FOR 0PERATICN i
j 2.1 Reactor. Coolant System (Continued)-
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2.1.3: Reactor Coolant Radioactivity (Continued e.
Graph'Of,the I-131 concentration and one other radioicdine 1sotope cuicentration in. microcuries per gram as a function-t of time for the duration of.the specific activity above thel steady-state level, i
Easis The limitations on the radioactivity of the reactor coolant ensure that.the.resulting 2-hour deses at the site boundary will be well within ths limits of 10 CFR Part. LOO following a steam generator tube rupture accident in conjunction with an assumed steady state t
primary-to-secondary steam generator leakage rate of 1.0 GPM and a concurrent loss.of offsite power.
Percitting' operation to continue for limited time periods with the reactor' coolant 4 radioactivity levels >1.0 pCi/gm DOSE EQUIVALENT.
q' I-131, but 5 60 pCi/gm, accommodate possible iodine spiking phenoment,n which may occur following changes in thermal power.
Reducing i, to < 530 F prevents the release of radioactivity should astecngd9atortuberupture,sincethesaturationpressureofthe reactor cootant is below the lift pressure of the atmospheric steam relief valves.
Tite' surveillance requirements provide adequate assurance that excessive radioactivity levels in the reactor coolant
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will be detected in sufficient time to take appropriate corrective sctions(s).
Rgerences USAR, Section 11.1.L 3
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USAR, Section 14.14 2-9 Amendment No. 60,67,I07,,119
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l1, 2.W IMITIh!G CONDIT @NS'FOR OPERATION 2.3 Emergency Ccm Cooling System App'ficability h5 Applies to the operating status of the emergency core cooling system.
Oy,(ective To assure operability of equipment required to remove decay heat from the core.
Specifications (1) Minimum Requirements The. reactor shall not be made critical unless all of the following conditions are met:
a.
The SIRW tank contains not less than 283,000 gallons of water with a boron concentration of at least 1800 ppm at a temperature not less then 50 F.
.l b.
One means. of temperature indication (local) of the SIRW tank is operabic.
c.
All four safety injection tuks aft operable and pressurized to at :least 240 psig with a tank liquid of at least 116.2 inches
-(67%) and a maximum level of 128.1 inches (74%) with refueling boron concentration.
d.
One level and one pressure instrument is operable on each safety injection tank.
e.
One low pressure safety injection pump is operable on each bus.
f.
One high pressure safety injection pump is operable on each bus.
g.
Boch shutdown heat exchangers and three of four-component cooling heat exchangers are operable.
h.
Piping and valves shall be operable to provide two flow paths from the SIRW tank to the reactor coolant system.
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i.
All valves, piping and interlocks associated with the above i
components and required to function during acrfdent conditions are oper,able.
HCV-2914, 2934, 2974, and 2954 uall have power removed from the motor operators by locking open the circuit breakers in the power supply lines to the valve motor operators.
FCV-326 shall be locked open.
1 2-20 Amendment No. 17,32.43,Ill3,II7,119
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-3*0.. SURVEILLANCE REQUIREMENTS-
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3.5 Containment Tests (Continued) b.
-Acceptance Criteria (i)
.The tendon force determined.by the lift-off test shall be consirjered adequate if.it is not less than the force shown on the appropriate lower limit curve of USAR Figure 5.10-3, as adjusted for wire removal, for'the l
elapsed time between the original prestressing and the particular surveillance period. ' These lower limit curves have been generated by calculating the difference between the anticipated tendon force at end of plant-life and.the minimum tendon force to meet the design requirements.
One half of this difference has been added to the anticipated total-loss of prestress at the end of plant life and the curves have been drawn to meet this' limit.
Since the lock-off force on individual tendons fs varied to compensate for elastic shortening of the. structure, the tendon forca at 70% of ultimate strength, rather than the actual lock-off fcrce'shall be taken as the initial prestress force.
An allowable limit of not more than one' defective tendon out cf the total sample population is acceptable, provided an adjacent tendon on each side of the Uefective tendon is tested and is found.to meet criteria.
Should one of the adjacent tendons be also found defective, the Commission shall be notified in accordance with Regula-tory Guide 1.16, " Reporting of Operating Information".
(ii)
No unexpected change in corrosion conditions or grease properties.
(iii) All three tensile tests on any one wire indicate an ultimate strength at least equal to the specified minimum ultimate strength cf the wire.
If'a single test on any one wire shows an ultimate strength less than the specified minimum,, the Commission'will be notified in accordance with Regulatory Guide 1.16,
" Reporting of Oper& ting Information".
c.
Correct'ive Action If the above acceptance criteria are not met, an immediate investigation shall be made to determine the cause(s) for the non-conformance to the criteria, and results will be reported to the Commission within 90 days.
d.
Test Fnquency The tendons in the prestressing system shall be inspected once every 5 years.
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3-46 Amedmeret No. 95,97, 119 u-_____-__
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[5.0'"ADMINISTRAIIVECONT,R_0M 5.1-Responsibility:
5.1.1 The Manager - Fort Calhoun' Station shall oe responsible for overall facility operation and shall delegate,in writing the succession to.
1 this responsibility during his absence.
5.2 Organization
- 5,2.1 'Onsite and offsite organizations shall.be established for unit i
operation a'nd corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting thi safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships',
and job descriptions for ke personnel positions, or in equivalent forms of documentation.
The requirements shall be documented in the USAR.
b.
The Manager - Fort Calhoun Station shall be responsible for overall unit safe operation and shall have control over those q
onsite activities necessary for safe operation and maintenance of the plant.
c.
The Senior Vice President - Nuclear Operations, Production Engi-neeri!ng, and (uality and Environmental Affairs shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
' d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Plant Staff The plant staff organization shall be as described in Chapter 12 of the
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USAR function as follows:
a.
Theiminimum number and type of licensed and unliceresed operating personnel required onsite for each shift shall be as shown in Table 5.2-1.
5-1 Amendment No. 53,76,78,101,2Z5,119 e
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50; ADMINISTRATIVE' CONTROLS C.
5.5.1.7 ;b.
Rencer determinations.in writing withL regard to whether or not each item considered under 5.5.1.6(a)'through (e) above J
constitutes an unreviewed safety question.
ic.
Provide immediate written notification to the Division Manager -
Nuclear Operations and the Safety Audit and Review Committee of disagreement between the Plant Review Comn,ittee.and the Manager -
Fort Calhoun Station; however, the Manager:- Fort Calhoun Station -
shall _ have responsibility for resolution of such disagreements pursuant-to 5.1.1 above.
I Records.
5.5.1.8 Yhe Plant Review Committee shall maintain written minytes of each meeting and copies shall be provided to the Division Manager - Nuclear Operations and Chairman of the Safety Audit and Review Committee.
5.S.2 Safety Au'dit and Review Committee (SARC)
Function-5.5.2.1 The Safety Audit and Review Committee shall function to provide the independent rev'iew and audit of designated activities in the areas of:
a.
nuclear power plant operation b.
nuclear engineering c.
' chemistry and radiochemistry d.
metallurgy-1 e.
instrumentation and control-f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance Composition 5.5.2.2 The $afety Audit and Review Committee shall be composed of:
Chairman:
Division Manage" - Quality and Environmental Affairs Member:
Senior Vice President - Nuclear Operations, Production Engineering and Quality and Environmental Affairs Member:
Division Manager - Nuclear Operations Member:
Division Manager - Production Engineering Member:
Manager - Fort Calhoun Station Member:
Manager - Emergency Planning Member:
Qualified Non-District Affiliated Consultants as Required and as Determined by SARC Chairman 5-5 Amendment No. 66,93,99,IBI.,ZZ5,119
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't 5.0 'p0MINISTRATIVECONTROLS 5.5.2.8 e.
The Fort-Calhoun Station Emergency Plan and implementing procedures at least once every twelve months.
j f.
The Site Security Plan and implementing procedoras at least once every twelve months.
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9 The Safeguards Contingency Plan and implementing procedures at j
least once every twelve months.
h.
The Radiological Effluent Program including the Radiological Environmental Monitoring Program and the results thereof, the Offsite Dose Calculation Manual and implementing procedures, and the Process q
Control Program for the solidification of radioactive waste at least once per 2 years.
i.
Any other area of facility operation considered appropriate by the Safety Audit and Review Commit?ee or the Senior Vice President -
Nuclear Operations, Production Engineering, and Q9ality and l
Environmental Affairs.
t Authority 5 5.2.9 Tto S',fety Audit and Review Committee shall report to and advise the Senior Vice President - Nuclear Operations, Production Engineering, and l
Quality and Envirenruental Affairs on those areas of responsibility 3
specified in Sections 5.5.2.7 and 5.5.2.8.
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5.5.2.10 Recerds of Safety Audit and Review Ccamittee activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each Safety Audit and Review Committee meeting shall be 4
prepared, approved and forwarded to the Senior Vice President -
f Nuclear Operations, Production Engineering, and Quality Assuraixe l
and Environmental Affairs within 14 dayf following each meeting.
b.
Reports of revies encompassed by Section 5.5.2.?e, f, g, h, and i above shall be prepared, approved and forwarded to the Senior Vice President - Nuclear Opereticas, Production Engineering, and l
l Quality Assurance and Environmental Affairs within 14 days following l
completion of the review.
c.
Audit reports encompassed by Section 5.5.2.8 above shall be forwarded to the Senior Vice President - Nuclear Operations, Production Engineering, and Quality Assurance and Ernironmental Affairs and to the responsible management positions designated by the Safety 4
1 Audit and Review Ccnmittee within 30 days af ter completion of the
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audit.
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5-8 Amer.dment No. EEB,93,102,II5,119 j
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5.9:1 Continued q
work and job functions,E
.g., reactor operations and surveil-e lance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and I
refueling outages.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the i
aggregate, at least 80% of the total whole body dose received 1
from external sources shall te assigned to specific major work j
functions.
c.
Monthly Operating Report.
Routine reports of operating statis-tics and shutdown experience shall be submitted on a monthly basis to the U. S. Nuclear Regulatory Lommission, Document Control Desk, Mail Station P1-137, Washington, D. C.
20555, with a copy 4
to the appropriate Regional Office, to arrive no later thar the fifteenth of each month following the calendar month covered
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by the report.
This muithly report shall also include a staterrent regarding any challenges or failures to the pressurizer power 1
operated relief valves or safety vaives etcurring during the f
subject month.
5.9.2 Reportab_1_e Event
'1 A Licensee Event Report (LER) shall be si:5mitted to the U.S. Nuclear Regulatory Commission, Document Contro? Desk, Mail Station P1-137, l
Washington, D. C.
20555 with a copy to Region IV of the NRC within I
30 days af ter discovery of any event nreeting the requirements of i
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l 2/ This tabulation supplements the requirements of f 20.407 of 10 CFC i
l Part 20.
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5-12 Amendment No. 9,24,35,85,99,119 i
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