ML19224D446
| ML19224D446 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-21-A-062, DPR-21-A-62) |
| Issue date: | 06/01/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19224D442 | List: |
| References | |
| NUDOCS 7907120179 | |
| Download: ML19224D446 (14) | |
Text
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s r g'o UNITED STATE:;
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,[,;
NUCLEAR REGULATORY COMMISSION y ". c. (((/ $
WASHINGTON. D. C. 20555
-;iD E
'n y
% ^f-* N s ; m J THE CCIINECTICUT LIGHT A!1D POWER COMPANY, THE HARIFORD ELECTRIC LIGHT COMPANY, WESTERN MASSACHUSETTS ELECTRIC COMPANY, AND NORTHEAST NUCLEAR Et1ERGY COMPANY DOCKET N0. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amencment No. 62 License No. DPR-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application fur amendment by the Connecticut Light and Power Company, the Hartford Electric Light Company, Western Massachusetts Electric Company, and Northeast Nuclear Energy Company (the licensees) dated June 8,1976, as supplemented by letter dated July 1,1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 common 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicatec in the attachment to this licer.se anendment, and paragraph 3.E of Provisional Operating License No. :?R-21 is hereby amended to read as +:llo.s:
g 115 7907120/7 9 g
. "B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
62, are hereby incorporated in the license.
flortheast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications."
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
~
e~ -
Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 1,1979
.-(!IG 3,
)LO
ATTACHMENT TO LICENSE AMENDMENT NO. 62 PROVISIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert iii iii
- 3/4 6-1 3/4 6-1 3/4 6-2 3/4 6-2 3/4 6-2a 3/4 6-3 (Figure 4.6.1) 3/4 6-3 (Figure 3.6.1) 3/4 6-3a(Figure 3.6.2) 3/4 6-3b(Figure 3.6.3)
B 3/4 6-1 B 3/4 6-la and B 3/4 6-lb B 3/4 6-2 8 3/4 6-2 Overleaf page 3/4 6-4 is provided for document completeness.
- This page is included for the purpose of correcting an administrative ecror which occurred inadvertently during the issuance of Amendment N1. 44, dated March 3, 1978.
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SURVEILLAtrE REQUIREMENT LIMITIfiG C0f4DITI0ft FOR OPERATI0ti 3.6 PRIMARY SYSTEM BOUTIDARY 4.6 PRIMARY SYSTEM B0UNDARY Applicability:
Applicability:
Applies to the operating status of the reactor Applies to the periodic examination and testing coolant system.
requirements for the reactor coolant system.
Objective:
Objective:
To assure the integrity and safe operation of To' determine the condition of the reactor coolant the reactor coolant system.
system and the operation of the safety devices related to it.
Specification:
Specification:
A.
Thermal Limitations A.
Thermal Limitations 1.
The average rate of reactor coolant 1.
During heatups and cooldowns, the follow-temperature change during normal heatun or cooldown shall not exceed ing temperatures shall be permanently 100' in any one-hour period.
recorded every 15 minutes, until three g
consecutive readings at each given loca-2.
At all times, the shell flange to shell tion are within 5 F.
temperature dif ferentia.1 shall not exceed a.
Reactor vessel shell.
'O 140 F.
b.
Reactor vessel shell flange.
c.
Recirculation Loops A and B.
B.
Pressurization Temperature d.
Reactor Vessel Shell adjacent to 1.
Inservice Hydro and Leak Tests shell flan.ge.
The reactor vessel shell-temperature during inservice hydro or leak testing B.
Pressurization Temperature shall be at or to the right of the solid-line curve (denoted as the cperating 1.
Inservice Hydro and Leak Tests zone) shown in Figure 3.6-1.
The dashed-line curve representing the RV shell belt-The reactor vessel shell temperature and 1ine region is included, since it will be the reactor shell temperature adjacent to l
increased by the expected shift in RTt4DT.
the shell flange shall be permanently recorded every 15 minutes during hydro-static or leak testing.
Amendment tio. JJ, 62 3/4 6-1
SUN EILLANCE REQUIREMENTS LIMITIriG CONDITION FOR OPERATION l
Normal Heatup and Cooldown_ and Lew-Level Physics 2.
tiormal Heatup_ and Cooldown and Low-Level
_ Tests 2.
Physics lests During heatup by non-nuclear means, and ccoldown During heatup by non-nuclear means following nuclear shutdown and low-level physics (mecha.>ical), and cooldown following tests, the reactor vessel shell and fluid ten-nuclear shutdown, and low-level physics peratures of Specification 4.6.A.1 shali Le tests, the reactor vessel shell and fluid permanently recorded every 15 minutes.
tenperatures of Specifications 4.6.A!l shall be at or to the right of the solid-line curve shown in Figure 3.6-2.
The 3.
Core Criticality dashed-line curve representing the RV shell During heatup and cooldown operations, with a bel tline region is included, since it will critical core (except for low-level physics be increased by the expected shif t in RTNDT.
tests), the reactor vessel shell and fluid temperatures of Specification 4.6. A.1 shall 3.
Core Criticality be pennanently recorded.
During all operation with a critical core, Reactor Vessel Heat Stud Tensioning 4.
except for low-levei physics tests, the reactor vessel shell and fluid temperatures When the reactor vessel head bolting studs are of Specification 4.6.A.1 shaTT be at or to the tightened or loosened, the reactor vessel head Led right of the solid-line curve shown in flange and heaa temperatures shall be permanently IN3 C7' Figure 3.6-3.
recorded.
[.
The dashed-line curve representing the RV 5.
Reactor Vessel Surveillance _
shell beltline region is included, since it will be increased by the expected shif t Mechanical test specimens r.
resenting the c?
reactor vessel base metal, weld metal and in RTNDT.
hea t-af fected zone metal and neutron flux installed in the reactor vessel gractor Vessel Head Stud Tensioning wires were 4.
at the core midplane level.
The reactor vessel head bolting studs shall not be under tension unless the temperature The first capsule containing the test specimens of the vessel head flange and the head is to monitor radiation effects will be removed about greater than 70 F.
from the vessel during a refueling outage at 10 EFPY.
The second capsule will be removed at 18 to 24 EFPY.
The surveillance program is in 3/4 6-2 accordance with GE Report NED0-10ll5 and ASTM E Ame-dment No. 62 185-66.
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A.
Thermal Limitations The reactor vessel has been analyzed for thermal conditions encountered durir.g heatup and cooldown operations conducted within thr. specified differential temperatures and rate limits.
Heatup and cooldown operatians througbaut plant life at uniform rates of 100"F/hr were considered
- 00 F tc 546 F and were shown to be within the requirements for in the temperature range stress intensity and fat 1 e limits of Section III of the ASME Boiler and Pressure Vessel 3
Code (1965 Edition).
The ailowable number of heatup and cooldown cycles has been determined It is as 12,000 for the reactor vessel closure region and 80 cycles for the clusure bolts expected that the reactor vessel will be subject to 120 heatup and cooldown cycles during the service lifetime.
B.
_ Pressurization Tempera ture Operating limits for the reactor vessel pressure and temperature during normal heatup and cooldown, and during inservice hydrostatic and leak testing were established using Appendix G, For of the Suniner 1972 Addenda to Section III of the ASME Boiler and Pressure Vessel Code.
the purpose of this analysis the reference temperature, RTNDT, of the reactor vessel material test data taken in accordance with the requirements of the Code to which is based on the impact che reactor vessel as designed and manuf actured.
For the reactor vessel beltline region, a For the remainder of the reactor vessel, a RTNDT RTHDT of +10"F based on impact data was used.
of +40 F was used as this is the maximum NDT temperature permitted by the reactor vessel purchase specification.
Figure 3.6-1 establishes the mininum temperature for hydrostatic and leak testing required by the ASME Boiler and Pressure Vessel Code,Section XI.
Test pressures for inser. ice hydrostatic and leak testing required by ASME Section XI (1974) are a function of the testing temperatures Accordingly, the maximum hydrostatic test pressures will be 1.1 and the c mponent material.
times the operating pressure or about 1139 psig for a reactor coolant temperature greater than (jJ
]QQ f, DJ Figure 3.6-2 provides 1fmitations for plant heatup and cooldown when reactor is not critical, C3' The thennal limitations consider maximum heatup and cooldown rates of 100 F/hr in any one-hour ia period.
These limits include a margin c.'
Figure 3.6-3 establishes operating limits when core is critical.
of 40 F as required by 10CFR50 Appendix G.
Fast neutron irradiation af fects the fracture toughness of the reactor vessel material.
In order to assure non-ducti.le failure, two types of _information are needed:
Amendment No. 62 03/4 6-la
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ring type of seal are designed to provide a leak-tight seal when bolted together.
When the vessel head is placed on the reactor vessel, only that portion of the iaad I
flange near the inside of the vessel rests on the vessel flange. As the head bolts are replaced and tensioned, the vessel head is flexed slightly to bring together the entire contact surfaces adjacent to the "0" rings of the head and vessel flange.
Both the head and the head flange have an NDT temperature of +10 F and they are not subject to any appreciable neutron exposure. Therefore, the minimum vessel head and head flange temperature for bolting is established as NOTT + 60 F = 70 F.
C.
Coolant Chemistry A radioactivity concentration limit of 20 pCi/ml total iodine can be reached if the gaseous effluents are near the limit es set forth in Specification 3.8.A.1 or there is a failure or shutdown of the cleanup demineralizer.
In the event of a steam line rupture outside the drywell the resultant. radiological dose at the site boundary would be about 10 rem to the thyroid.
This dose was calculated on the basis of a total iodine activity limit of 20 pCi/cc, meteorology corresponding to Type f conditions with a one meter per second wind speed, and a valve closure time of five seconds.
If the valve closed in ten seconds, then the resultant dose would increase to about 30 rem.
The A reactor water sample will be used to assure that the limit of Specification 3.6.C.1 is not exceeded. In total radioactive iodine activity would not be expected to change rapidly over a period of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.
addition, the trend of the stack of f-gas release rate, which is continuously monitored, is an indication of the trend of the iodine activity in the reactor coolant.
Since the concentration of radioactivity in the reactor coolant is not continuously measured, coolant sam-pling would be ineffective as a means to rapidly detect gross fuel element failures.
Howeser, capability to de'.ect gross toel element failures is provided by the radiation monitors in the off-gas system and on the main steam lines.
the primary systen are primarily 304 stainless steel and the Zircaloy fuel cladding.
The u
ry Materials in Limits are placed on reactor water chemistry limits are established to prevent damage to these materials.
Gw chloride concentration and conductivity.
The most important limit is that placed on chloride concentration prevent stress corrosion cracking of the stainless steel.
According to the data, the established limit
~
t is conservative.
Zircaloy does not exhibit similar stress corrosion failures.
r B 3/4 6-2 Amendment No. 62
SURVEILLANCE K0UIREMif1T L1"1ilim EONDIT105 FOR OPERATION I h.
reactor coolant water shall not exceed 2.
Durinq start ns and at < teaming rat ;
below 100,00i, pounds per hour, a sample the following limits with steaming rates of reactor coolant shall be taken every l i. r '. than 100,000 pounds per hour except as four hours and analyzed for conductivity speci fird in 3.6.C.3:
and chloride content.
Coruluc t iv i ty 2 nmho/cm With s teaming ra tes grea ter than 3.
a.
Chloride ion 0.1 ppm or equal to 100,000 pounds per hour, a reactor coolant sampte For reactor startups, the maximum value for shall be taken at least every c ondur.t i v i t y shall not exceed 10 u ho/cm 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and when the continuous m
an.! t he maximun value for chloride ion con-conduc tiv i ty moni tors i ndica te c ont ra t i m shall not exceed 0.1 ppa for the abnormal conductivity (other than
'i:
i o r' a f t or pl a t i tu) t he rea r. tn r in short-torn spikes of one minute or
.p catinq condition, in n ) and anal yzed for conduc tivi ty rw p or and chlorido ion content, t
. pe r. i f i ed i n 3. 6.C. 3 a bov e,
1
. tent a r.
r c c. t t o r c:o o l a n t water shall not exceed the The reactor coolant conductivity b.
1 %its with steaming rates oqual shall be monitored continuously.
followinq to or great than 100,000 pounds per hour D.
Coolant Leakage 2.0 n ho/cm m
f.o nduc t i v i ty Chloride ion 0.5 ppm Reactor coolant system leakage into the primary containment shall be checked and If Specification 3.6.C.1, 3.6.C.2, 3.6.C.3 recorded a t least once per day, or !.6.C.4 is not met, an orderly s. stdown shall bo initiated.
D.
Coolant t<al. m v.i r -
i r r.nlia t ed fuel is in the reactor ve'.-
'n(
Auf i n,n -
coolant leakage into the primary
~
.ci, i na c t.o r
<.ontainment from unidentified sources shall not iO ep.ced i' a qpm.
In addition, the to ta l reactor c?
3/4 6-4