ML19209A263
| ML19209A263 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/19/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209A259 | List: |
| References | |
| NUDOCS 7910030247 | |
| Download: ML19209A263 (19) | |
Text
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[ga arog*'o, UNITED ST/.72S E '
.,( ' 'g NUC1. EAR REGULATORY COMMISSION E
WASHING TON. D. C. 20655 s,
/
....+
CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY WESTERN MASSACHUSETTS ELECTRIC COMPANY NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO.1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 64 License No. DPR-21 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company, and the Northeast Nuclear Energy Company (the licensees) da ted Mr' 27, 1977, complies with the standards and requirements of the Atot c 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 comon 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.
1087 175 7 91003 01N7 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B of Provisional Operating License ilo.
DPR-21 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through knendment No. 64, ar' hereby incorporated in the license. Northeast f-
?ar Energy Company shall operate the facility in act., _ance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMt1ISSION T
E.m W
Dennis L. Zieman Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 19, 1979 1087 176
ATTACHMENT TO LICENSE AMENDMENT NO. 64 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Remove the following pages of the Appendix "A" Technical Specifications and insert the enclosed pages. The revised pages contain the captioned amendment number and vertical lines indicating the area of change.
PAGES iii 3/4 6-5 3/4 6-6 3/4/ 6-7 3/4 6-8 3/4 6-9 3/4 13-1 (New) 3/4 13-2 (New)
B 3/4 6-5 B 3/4 6-6 B 3/4 6-7 B 3/4 6-8 B 3/4 6-13 8 3/4 6-14 8 3/4 13-1 (New)
Overleaf page 3/4 6-10 is provided for document completeness.
1087 177
Surveillance
_Page No.
3/4 7-13 C.
S e c o n d a ry Co n t a i n me n t................................... C.....................
3/4 7-14 D.
P rimary Conta inment Isol a ti on Va l ves.................... D.....................
~
4.8 3.8 RADI0 ACTIVE MATERIALS 3/4 8-1 A.
A i r b o rn e E f fl u e n t s...................................... A....................
3/4 8-3 B.
Mechanical Vacuum Pump..................................B..........
3/4 3-4 C.
Liquid Effluents........................................C...
3/4 8-5 D.
Ra di oa c ti ve Was te Stora ge............................... D.....................
4.9
- 3/4 9-1 3.9 AUXILIARY ELECTRICAL SYSTEMS 4.10 3.10 REFUELING 3/4 10-1 A.
Re fuel i n g I n te rl ocks................................. A.
3/4 10-2 B.
Core Monitoring........................................ 8.....................
3/4 10-2 C.
Fuel S to ra ge Pool Wa te r Le vel........................... C.....................
3/4 10-2 Crane Operability.......................................D.....................
3/4 10-2 0.
Crane Travel - Interlocks and Swi tches..................E.....................
E.
4.11 3.11 REACTOR FUEL ASSEMBLY 3/4 11-1 Average Planar Linear Hea t Genera tion Ra te.............. A.....................
3/4 11-8 A.
Linear Heat Generation Rate............................ 8.....................
3/4 11-9 B.
C.
Minimum Critical Power Ratio............................C.....................
3/4 12-1 3.12 FIRE PROTECTION SYSTEMS 3.13 INSERVICE INSPECTION 4.13 3/4 13-1 l
5.0 DESIGN FEATURES 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility.............................................................. 6-1 6.2 Organization.................................................................
6-2 6.3 Fa c i l i ty S ta f f Qu al i fi ca ti o n s................................................
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iii Amendment No. J#, #3, ##, #5, fl,64 CD
SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION E.
Safety and Relief Valves coolant system leakage into the primary con-tairinent shall not exceed 25 gpm. If these conditions cannot be met, initiate an orderly 1.
Three of the relief / safety valves top works shall be bench checked or replaced shutdown and have the reactor in the cold 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 shall be checked or replaced every two E.
Safety and Re11ef Yalves refueling outages. The set pressure shall be adjusted to correspond with a 1.
During power operation and whenever the steam set pressure of:
reactor coolant pressure is greater than 90 psig, and temperature greater than No. of Valves SetPoint(psig) 320*F. the safety valve function of the six relief / safety valves shall be operable.
1 1095 1 1%
(The solenoid activated relief function of 1
1110 + 1%
the relief / safety valves shall be operable 4
1125 ~1 11 as required by Specification 3.5.0) 2.
At least one of the relief / safety valves shall be disassembled and inspected each 2.
If Specification 3.6.E.1 is not met, initiate refueling outage.
an orderly shutdown and have the reactor coolant pressure below 90 psig and tempera-3.
Dur'ng each operating cycle with the reactor 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 />.
at low pressure, each safety valve shall be manually opened until operability has been verified by torus water level instrumenta-F.
Structural Integrity tion, or by an audible discharge detectM by an individual located outside the tcqJs The structural integrity of the primary system in the vicinity of each discharge.
boundary shall be maintained as specified in Technical Specification 3.13.
F.
Structural Integrity Inservice Inspection and Testing of prinary O
system boundary components shall be perfonned co as specified in Survef11ance Requirement 4.13.
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LIMITING COND1rION FOR OPERATION SilRVEILLANCE REQUIREMENT G.
Jet Pumps G.
Jet Pumps 1.
Whenever the reactor is in the Startup/ Hot i.
Whenever there is a recirculation flow Standby or Run modes, all jet pumps shall with the reactor in the startup/ hot be intact and all operating jet pumps shall standby or run modes, jet pump inte-be operable.
If it is determined that a grity and operability shall be checked jet pump is inoperable, an orderly shutdown daily by verifying that the following shall be initiated and the reactor shall be two conditions do not occur in a cold shutdown condition within 24 simultaneously:
- hours, a.
The recirculation pump flow 2.
Flow indication from each of the twenty jet differs by more than 10% from the pumps shall be verified prior to initiation established speed-flow of reactor startup fran a cold shutdown characteristics.
condition.
b.
The indicated total core flow is 3.
The indicated core flow is the som of the more than 10% greater than the flow indication from each of the twenty jet core flor value derived from pumps.
If flow indication failure occurs established power-core flow for two or more jet pumps, immediate correc-relationships.
tive action shall be taken.
If flow indica-tion cannot be obtained for at least nine-2.
Additionally, when operating with one teen jet pumps, an orderly shutdown shall recirculation pump with the equalizer be initiated within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the reactor valves closed, the diffuser to lower shall be in a cold shutdown condition within plenum differential pressure shall be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
checked daily, and the differential pressure of any jet pump in the idle H.
Recirculation figy_ Flow Mismatch loop shall not vary by more than 10%
from established patterns.
1.
Wheneur t,oth recirculation pumps are in operation, pump speeds shall be maintained 3.
The baseline data required to evaluate within 10s of each other wher, power level the conditions in Specifications is greater than 80% and within l$f of each 4.6.G.1 and 4.6.G.2 will be acquired other wher power level i s l es s,t ha n 80 ',.
each operating cycle.
H.
Recirculation pump speed shall be checked daily for mismatch.
C CO Amendment No.16
-J 3/4 6-10 M
b
LIMITING CONDITION FOR OPERATION SURVEILL,ANCE REQUIREMEhi 3.13 INSERVICE INSPECTION 4.13 INSERVICE INSPECTION Applicability Applicability Applies to ASME Boiler and Pressure Vessel Code Applies to the perioute inservice inspection Section III Class 1, 2, and 3 equivalent components, and testing of ASME Boiler and Pressure Vessel Code Section III Class 1, 2, and 3 equivalent components.
Objective To assure tFe structural integrity of the applica-Objective ble components defined above.
To verify the structural integrity of the appli-cable cc;ponents defined above.
Specification Specification The structural integrit of ASME Code Class 1, 2, and 3 equivalent components shall be maintained at an A.
Inspections acceptable level in accordance with 10CFR50.55a(g).
Inservice inspection of ASME Boiler and Pres-sure Vessel Code Section III Class,1. Class 2, and Class 3 equivalent components shall be perfonned in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.55a(g) with the exenptions and al-ternate inspections that have been approved by the NRC pursuant to 10CFRSO, Section 50.55 a(g)(6)(1). These exemptions and alternate inspections are included in the Inservice Inspection Program.
cD cx3 B.
Testing N
Inservice testing of ASME Boiler and Pressure Vessel Code Section III Class 1 Class 2, and cc Ln 3/4 13-1 Amendment No.64
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT Class 3 equivalent pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, Section 50.55a(g), with the exemptions and al-ternate testings that have been approved by the NRC pursuant to 10CFR50, Section 50.55a(g)(6)(1). These exemptions and alternate testings are included in the Inservice Inspection Program.
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Oc ox 3/4 13-2 Amendment No. 64
When the setpoint is being bench checked. it is prudent to disassemble one of the relief / safety valves to examine for crud buildup, bending of certain actuator members,or other signs of possible deterioration.
Testing at low reactor pressure is required during each operating cycle. It has been demonstrated that the blowdown of the valve to the torus causes a wave action that is detectable on the torus water level instrv-mentation. The discharge of a safety valve is audible to an individual located outside the torus in the vicinity of the line, as experienced at other BWR's.
F.
Structural Integrity See Bases Section 3.13 and 4.13 cD co N
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Amendment No. g, 64 8 3/4 6-5
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B 3/4 6 7 Amendment No. 64 1
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Jet Pumps Failure of a jet pump nozzle assembly holddown mechanism, nozzle assembly and/or riser increases the cross sectional flow area for Slowdown following the postulated design basis double-ended recirculation line a
break. Therefore, if a failure occurs, repairs must be made to assure the validity of the calculated co y
consequences.
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8 3/4 6-14 Amendment No. 64 e
3.13 and 4.13 Bases Inservice Inspection On April 26, 1976, the NRC informed Northeast Nuclear Energy Company of revisions to 10CFR50, Section 50.55a which require that Inservice Inspection and Testing be performed in accordance with ASME Section XI Code and applicable Addenda, with exceptions where specific relief is granted to a licensee by the NRC. 10CFR50, Section 50.55a(g) also requires that Technical Specification changes be made to indicate compliance with the ASME Section XI Code and applicable Addenda.
The Limiting Condition for Operation of ASME Boiler and Pres:Lre Vessel Code Section III, Class 1, 2, and 3 equivalent components assures that such components will be inspected and testing in accordance.
with the ASME Section XI Code and Applicable Addenda, except where specific written relief is granted by the NRC. Relief is requested from the NRC when Code requirements are impractical to follow, pursuant to 10CFR50.55a(g)(6)(i).
The detailed procedures for inspections and testing of components is documented in the Inservice Inspection Program.
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