ML20042C036

Amend 73 to License DPR-65,changing Tech Specs to Allow Reactor Heatup for Cycle 5 Operation W/Less than 100% Insp of Tubes in Each Steam Generator

ML20042C036
Person / Time
Site:	Millstone
Issue date:	03/05/1982
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20042C037	List: ML20042C036 ML20042C038 ML20042C042
References
TAC-47577, NUDOCS 8203300102
Download: ML20042C036 (7)

Text

_

UNITED STATES

[ ' j

.,-q o,j 4

NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D. C. 20555

-/- -

,E

• b M [j 4, v NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-3_36 MILLSTONE HUCLEAR POWER STATION, UNIT' N0. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. DPR-65 1.

The Nuclear Regulatory Commission (the Commission) has foun.d that:

A.

The application for amendments by Northeast Nuclear Energy Company (the licensee) dated January 12 and liarch 4,1982, as supplemented by letters dated January 22, February 5,12 and March 1,1982, complies with the standards and requirements of the Atomic Etargy Act of 1954, as arended (the Act) and the Commission's rules and regulatiens set forth in 10 CFR Chapter I; 5.

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission:

C.

There is reasonable assurance (i) that the activities authori:ed by this amend ent can be conducted without endangering the health and safety of the ouDlic, and (ii) that such activities will be conducted. in co.oliance sith tne C0rnission's regulations; Tne issuance of tnis arencment will not be inimical to :7e common defense and security or to the health and safety of. the public; and E.

The issuance of this amendment is in accordance wit 10 CFR Part 51 c.* the Commission's regulations and all applicable requirements have been satisfied.

8203300102 820305

/PDR ADOCK 05000336 "P

PDR

i

2.. Accordingly,-the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-65 is:hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 7 3, are hereby incorporated in the license. The licensee shall-cperate the facility in accordance with the Technical Specifications.

3.

This license anendnent is effective as of the date of its issuance.

1 FORTHENUCLEARNEGULATORYCOMMISSION W

Robert A. Clark, Chief Operating Reactors Branch 43 Division of L'icensing

Attachment:

Changes to the Technical Specifications f

Date of Issuance: MAR 5 352 Y

S O

F c

w

ATTACHMENT TO LICENSE AMENOMENT NO. 7.3 FACILITY OPERATING LICENSE NO. DPR-65 DOCKET NO. 50-336 Remove and replace the folicwing pages of the Appendix A Tecnnical Specifi-The revised pages are identified by cations with the enclosed pages. Amendment number and contain vertical lines ind

-The corresponding overleaf pages are also provided'to maintain document completeness.

Reciace_

Remove 3/4 4-7f 4 4-79

/4 4-7h 3/4 7-3

.-o...

o E

e i

t e

e i

~

s

+

N TAllLE 4.4 6

~

r-v1

-t Sil AM GLNLitA10ll Tulle INSPECTION O

ro 2ND SAMPLE INSPECTION 3flD SAMPLE INSPECTION ISI SAMi'l L IN:;PECllON Sainple Sire lhsult Actuen thsiuiseit liesult Actum flequirni liesult Action Requised y

a s.

A ininiintun of t:.I None N/A N/A N/A N/A to S Tulics per S. G.

C 2 Plug tiefes iive tubes C1 Nore N/A N/A

.4 asul snasco.ul.htional Plug elefective tubes C-1 None 2S tubes in tliss S G.

C-2 aiul nispect additional C-2 Plug defective tubes 4S tubes in this S. G.

Perform action for C-3 C-3 result of first w

sarnple

• • =

Perform action for s.

C -3 C-3 result of first N/A N/A u'

sainple N

C3 inspect all tubes in All other this S. G., ploy de S. G.s are None N/A N/A fcctive tubes and C-1 l

Perfoon action for N/A N/A

...I iti L - 2 I ut no C -2 sesult of secosul

.ulihhonal gn, pig.

]

Proinpi notifia.ation S. G. are

,i y,

e to UllC poi,uant C3 a

C1 to specilicati""

Adihtional Inspect,all tubes in a

6U3 S. G. is C--3 cach S. G. and pluy defective tubes.

• Prompt notification N/A N/A 2

.o to NilC pursuant to specilication n

n.9.1 N

N Wil016' N is titi? rHissilH'r all *.It' ant QI*iu'rall>f s is) the linit, it H1 n is the ritHinIter of sts?ain tjenerators inspected ta y

o' iloting an nr.pection

.ui

• For the Cycle 5 ref ueling outage only, action required for result C-3 is to inspect all tubes ru in the af fected area of both ste.un generators as identified in Figures 1 through 4 of the licensee's submittal of February 12, 1982.

The a f fected area of each tube is between the tube sheet and the first tube support in both hot and cold leg sides.

1

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:

A containment atmosphere particulate radioactivity monitoring a.

system, b.

The containment sump level monitoring system, and A containment atmosphere gaseous radioactivity monitoring i

c.

L system.

APPLICABILITY: MODES 1, 2, 3 and 4.

' ACTION:

With one of the above radioactivity monitoring leakage detection a.

systems inoperable, operations may continue for up to 30 days provided:

1.

The other two above required leakage detection systems are OPERABLE, and 2.

Appropriate grab samples are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

b.

With the containment sump level monitoring system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in CCLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

1 SURVEILLANCE REOUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:

Containment atmosphere gaseous and particulate monitoring systems-a.

performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL-TEST at the frequencies specified in Table 4.3-3, and b.

Containment sump level monitoring system-performance of CHANNEL CALIBRATION TEST at least once per 18 months.

~

MILLSTONE - UNIT'2 3/4 '4-8

aa

-~

s

- i 9

PLANT SYSTEMS ACTIVITY LIMITING CONDITION FOR OPERATION I

b.7.1.4 The specific activity of the secondary coolant system shall be 1 0.10 uCi/ gram DOSE EQUIVALENT I-131.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the specific activity of the secondary coolant system > 0.10 uCi/

gram DOSE EQUIVALENT I-131, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after detection.

SURVEILLANCE REQUIREMENTS

.7.1.a The specific activity of the secondary coolant system shall be determined to be within the limit by performance of the sampling and analysis program of Table 4.7-2.

l L

l MILLSTONE - UNIT 2 3/4 7-7

~

4 TABLE 4.7-2 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY' SAMPLE AND ANALYSIS PROGRAM TYPE OF MEASUREMENT MINIMUM AND ANALYSIS FREOUENCY 1.

Gross Activity Determination 3 times per 7 days with a maximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> between samples.*

I 2.

Isotopic Analysis for DOSE a) 1 per 31 days, when-EQUIVALENT I-131 Concentration ever the gross activity detennination indicates iodine concentrations

-greater than 10% of.

-e the allowable limit.

b) l per 6 months, when-ever the gross activity determination indicates iodine concentrations below 10% of the allowable limit.

• During Cycle 5 operation, the gross activity of each steam generator shall be determined daily to monitor the extent, if any, of primary to secondary leakage. The following reports shall be provided to the assigned NRC Project Manager:

a.

The baseline primary to secondary leakage rate of each steam generator as determined within two weeks after reaching equili-brium. aperation in Mode.1, and Ia - subse:;ect i cre ental 'ncreast cf 1 0. : ght n :ne equilibrium primary-to-secondary leak rate per steam generator be reported verbally within.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with a writ:5n ' folicwup report within 14 working days.

Whenever possible, all leak rate determinations shall be made at steady state operating conditions.

^

MILLSTONE - UNIT 2 3/478 eAmendment No. 7 3 -

g i

.