ML20031F397
| ML20031F397 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/06/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031F392 | List: |
| References | |
| NUDOCS 8110190745 | |
| Download: ML20031F397 (8) | |
Text
1 casc oq[o UNITED STATES g
j NUCLEAR REGULATORY COMMISSION e
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WASHINGTON. D. C. 20555 4
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NORTHEAST NUCLEAR ENERGY COMPANY DOCKET N0. 50-245 MILLSTONE UNIT N0. 1 AMENDMENTTOPROVISIONALOPERdTINGLICENSE Amendment No. 79 License No. DPR-21 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by the Northeast Nuclear Energy Company (the licensee) dated September 16, 1980, as revised,by Northeast
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Nuclear Energy Company telephone coments on September 16, 1981, cornplies with the standards and requirements'of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The. facility will operate in conform.ity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There i.s 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 Qill 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
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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, tne license is amended by changing Paragraph 3.B to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 79, are hereby incorporated in the license.
The licensee shall operate the facility in ac.cordance with the Technical Specifications.
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3.
This license amendment is effective as of the date of its issuance.
FOR,THE NUCLEAR REGULATORY COMMISSION enn s t. Crutchfield, CF ef Operating Reactors Branc #5 Division of Licensing
Attachment:
Changes to the Technical
. Specifications Date of Issuance:
October 6, 1981 e
/
o 6
9
AT_TACHMENT TO LICENSE AMENDMENT NO. 79_
PROVISIONAL OPERATING LICENSE N0. DPR-21 DOCKET N0. 50-245 Replace che following pages.of Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
3/4 6-5 6-1 6-4 6-25 iv t
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Pago N).
l 6.4 Training............................................................
6-5 6.5 Review and Aud1t....................................................
6-5 6.6 Re por tabl e Occurrence Ac ti on.........,.............................. 6-15 6.7 S a fe ty L im i t V i ol a ti o n.............................................. 6-15 6.8 Procedures..........................................................
6-16
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6.9 Reporting Requirements..............................................
6-17 6.10 Record Retention......................................:.............
6-22 6.11 Radiation Protection Program........................................
6-23 6.12 High Radiation Area..........'...............................
....... 6-23 6.13 Envi ronmental Quali fication.........................................' 6-25 6.14 Systems Integrity...................................................
6-25 6.15 Iodine Monitoring................................................... '6-25 0
t I-1 Amendment No.
,jpf, 79 jy Millstone Unit 9
1
t LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT coolant system leakage into the primary con-E.
-Safety' and Relief Valves tainment shall not exceed 25 gpm If these conditions cannot be met, initiate an orderly 1.
Three of the relief / safety valves top shutdown and have the reactor in the cold works shall be bench checked or replaced with a bench checked top works each re-shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
fueling outage. All six valves top works l
shall be checked or replaced every two E.
Safety and Relief Valves refueling outages.
The set pressure 1.
During power operation and whenever the shall be adjusted to correspond with a reactor coolant pressure is greater than st'eam set pressure of:
90 gsig, and temperature greater than No. of Valves SetPoint(psig[
320 F, the safety valve function of the l
six relief / safety valves shall be operab e.
1 1095 + 1%
(The solenoid activated relief function of 1
1110 + 1%
the relief / safety valves shall be operable 1125 T 1%
4 as required by Specification 3.5.D.)
2.
At least one of the relief / safety vahes, If Specification 3.6.E.1 is not me't, initiate 2.
shall be disassembled and inspected each an orderly shutdown and have the reactor coolant pressure below 90 psig and. tempera-refueling outage.
0 ture below 320 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l 3.
During each operating ' cycle with the reactor 3.
When the safety / relief valves are required at low pressure, each safety valve shall be to be operable per Specification 3.6.E.1, manually ope:1ed until operability 'ias been the Acoustic Valve Position Indication shall verified by torus water level
'as' rumenta-be operable.
Two of the six channels may tion, or by the Acoustic Valve Position l
be out of service provided backup indication Indication System, or by an audible discharge for the affected valves is provided by the deracted by an individual located outside the torus in the vicinity of each discharge.
Valve Discharge Temperature Monitor.
g 4.
If Specification 3.6.E.3 is not met, reactor 4.
The Acoustic Valve Position India tion operation is permissible only for the System shall be functionally tests:f once succeeding 30 days unless the Acoustic every three months, and calibrated once Valve Position-Indication System is made per operating cycle.
operable sooner.
shall be calibrated at least once every 18 months.
Amendment No. 29, M, H, D, 79 3/4 6-5 1:
l Millstone Unit 1 6.0 ADW.!NISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Superintenden.t shall be responsible for overall operation cf the Millstone Station-Site while the Unit Superintendent shall be respon-sible for operation of the unit.
The Station Superintendent and Unit Superin-tendent shall each' delegate in writing the. succession to these responsibilities during their absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown in Figure 6.2-1.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
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a..
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the-control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
e.
All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel Handling who has no other concurrent responsibilities during this operation, f.
A Fire Srigade of 3 members shall be maintained onsite at all times. The Fire Ericade shall not include the minimum shift crew necess'ary for s'fe shutdown of the Unit (2 members) or any a
personnel required for other essential functions during a fire emergency.*
6.3 FACILITY STAFF QUAllFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Health Physics Supervisor who~ shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, and (2) the Shift Technical Advisor who shall have a Bachelo'r's Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
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' ~ AmendmentNo.Jf,JE,(f.Akh79 6-1
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TABLE 6.2 MINIMUM SHIFT CREV COMPOSITION
- APPLICABLE MODES LICENSE CATEGORY 1, 2. & 3" 4 & Set SOL 1
1*
OL 2-1 Non-Licensed 2
1 i
None Required Shift Technical Advisor
- Do:s not include the licensed Senior Reactor or Senior Reactor Operator Limited to Fuel Handlinn individual supervision CORE ALTERATIONS after the initial fuel loadin'g.
- Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to accommodate injury.or sickness occurring to on duty shift crew members.
- Reactor Mode Switch Position is in RUN (any average coolant temperature)
STARTUP/ HOT STAND;Y (any cverage coolant temperature), and HOT SHUTDOWN (everage coolant temperature greater than 212*F). respectively.
- Reactor Mode Switch Position is in SHUTD0yN (average coolant temperature less than 212*F) and REFUELING (average coolant tempe,rature less than 212*F).
respectively.
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Mendment No.
Ji 79 6-4 l
5.13 EhTIR0hMENTAL OUAbFICATION A.
By no.later than June 30, 1952 all safety-related ele:trical equi;xnent
.in the facility shall be qualffied in accordance with the provisions of:
' Division.of Operatin; Reactors " Guidelines for Evaluating Environ:nental,
Qualification of Class IE Ele:trical Equipment in Operating Reictors" (DDR Guidelines); or, NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipent", De: ember 1979.
Copies of these docu:ents are attached to Order for Kodification of License DPR-21 dated.0ctober 24,1980.
B.
By.no later than Dece:ber I,1980, complete and auditible re:ords must be available and maintained at a central location which describe the environmental qualification pethod used for all safety-related.
electrical equipment in sufficient detail to document the degree of compliance,with the DDR Guidelines or NUREE-05BB. Thereafter, such
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records sho61d be uphted and maintained current as equignent is replaced., further tested, or otherwise further qualified.
6.14 SYSTEMS INTEGRITY The' licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
1.
Provisions establishing preventive maintenance and periodic visual inspection r quirements, and 2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
6.15 IODINE MONITORING l-The licensee shall implement a program which will ensur.e the capability to accurately determine the airborne iodine concentration in vital areas under accident' conditions.
This program shall include the following:
1.
Training of personnel, 2.
Procedur.es for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
l Order dated October 2,4, 1980 T
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Amendment No. 79 6-25
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