ML20071D213

Amend 75 to License DPR-28,changing Tech Specs Re Limiting Conditions of Operation for Standby Liquid Control Sys & Administrative Controls

ML20071D213
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	02/17/1983
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Vermont Yankee
Shared Package
ML20071D214	List: ML20071D213 ML20071D219 ML20071D229
References
DPR-28-A-075 NUDOCS 8303090257
Download: ML20071D213 (11)

Text

_______-____

,spung

['

,fg UNITED STATES 3

'3 g

NUCLEAR REGULATORY COMMISSION

- l WASHINGTON. D. C. 20655

\\...../

VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION y

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 75 License No. DPR-28 1.

The Nuclear Regulatory Comission (the Comission) has found that:

The applications for amendment by Vermont Yankee Nuclear Power Corporation A.

(the licensee) dated July 22, September 27 and December 7,1982 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended the (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 Comission; C.

There is reasonable assurance (i) that the activities authorized by this smendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Comission'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.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-28 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 75 are hereby incorporated in the license. The licensee shall operate the facility in accordance 4

with the Technical Specifications.

]

J G303090257 830217 2

gDRADOCK 05000271 3

PDR l

)

\\

2 3.

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

FOR THE NUCLEAR REGULATORY COP 9tISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Attaclaent:

Changes to the Technical Specifications Date of Issuance:

February 17, 1983 4

e b

O

ATTACHMENT TO LICENSE AMENDMENT NO. 7s FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-211 Revise the Technical Specifications as.follows:

REMOVE INSERT 39A 39A 80 80 190 190 190a 190a 1 91 1 91 192 192 194 194 206 206

l l

vyNes l

l TABt'E 3.2.1 l

RECTRCUt.ATION PUNP TRIP ACTUATION INSTRUMENTATION Recirculation Pump Trip - A & B (Note 1)

Nizimus Number of l

Operable Instrument Required.ktion When Minieme Channels per Trip Conditions for Operation are Syntes Trip Function Trip I4 vel Setting not satisfied 2

taw-fow Reactor Vessel h

6' 10.5" above top Note 2 Water Invel of enriched fuel l

2 Nigh Reactor Pressure 6 1150 psig Note 2

,2 Time Delays g

10 seconds Note 2 1

Trip Systems Iagic Note 2 I

f i

i Amendment No. Jif. M -)8', 75 4

j o

.I

VYNPS 3.4 LIMITI!!C CONDITIONS FOR OPERATION 4./ SURVEILLANCE REQUIREMENTS 9

Disassemble and inspect one explosion valve so that it can be established that the valve is not clogged. Both valves shall be inspected in the course of two operating cycles.

Test that the setting of the system pressure relief valves is between 1400 and 1490 psig.

B.

Operation with Inoperable Components B.

Operation with Inoperable Components, From and after the date that a redundant When a component becomes inoperable its redundant component is made or found to be inoperable, component shall be demonstrated to be operable reactor operation is permissible during the immediately and daily thereafter.

succeeding seven days unless such component is sooner made operable.

C.

Liquid Poison Tank - Boron Concentration C.

Liquid Poison Tank - Boron Concentration The liquid poison tank shall contain a boron The solution volume and temperature in the tank

'j bearing solution that satisfied the volume shall be checked at least daily.

concentration requirements of Figure 3.4.1 and k

the solution temperature, including that in the Boron concentration shall be determined at least pump suction piping, shall be not less than the once a month and at any time water or boron are temperature presented in Figure 3.4.2.

added or if the solution temperature drops below the limits specified by Figure 3.4.2.

D.

If Specification 3.4 A or B are not met an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown candition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If S ecification 3.4.A. E, nr C are not met, E.

P action shall be f wnediately initiated to correct the deficiency. If at the end of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> the system has not been restored to full operability, 1

then a shutdown shall be initiated with the reactor in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initial discovery.

80 1

1 Amendment No. 75

p VYNPS 6.0 ADMINISTRATIVE ODNTROLS Administrative controls are the written rules, or era, instructions, procedures, policies, practices designation of authorit'ies and responsibilities by the management to obtain assurance of safety and quali

, and the operation and maintenance of a nuclear power reactor.

These controls shall be adhered to.

6.1 ORGANIZATION A.

The Plant Manager has on-site responsibility for the safety and efficient operation of the facility.

Succession to this responsibility during his absence shall be delegated in writing.

+

B.

The portion of the corporate management which relates to the operation of this plant is shown in Figure 61 1

~

C.

In all matters relating to the operation of the plant and to those Technical Specifications, the Plant Manager shall report to and be directly responsible to the Manager of Operations.

9 D.

minimum conditions (see Table 6.1.1). Conduct of operations of the plant is shown in Figure 6.1.2 and wi j

1.

A licensed Senior Operator and an individual qualified in radiation protection procedures shall be present on-site at all times when there is fuel in the reactor.

2.

Licensed Operators on-site shall be in accordance with Table 6.1.1, one of which must be in the Control Room at all times when fuel is in the reactor.

3.

A licensed Senior Operator shall be in charge of any refueling operation.

4.

Qualifications with regard to educational background experience, and technical specialities of the supervisory personnel listed below shall apply and be maintained in accordance with the levels described in the American National Standards Institute N18.1-1971, " Selection and Training of Personnel for ph Power Plants".

a.

Plant Manager,

f.

b.

Operations Superintendent Operations Supervisor g.

Reactor and Computer Supervisor Technical Services Superintendent h.

Maintenance Supervisor j

c.

d.

Maintenance Superintendent i.

}

Instrument ar.d Control Supervisor Chemistry and Health Physics j.

Shif t Supervisors e.

i.

Supervisor i

e i

190

}

Amendment No. 66, 75 i

f 1-t VYNPS

.e 5.

The Chemistry and Health Physics Supervisor or Plant Health Physicist shall meet or exceed the qualifications l'.

of Regulatory Guide 1.8, Revision 1 (September 1975).

6.

The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scler.tific or engineering discipline with specific training in plant design, and response and anal} sis of the pla-* for transients and accidents.

1. This excludes 2 members of the A Fire Brigade of at least 5 members shall be maintained on-site at all times.

E.

minimum shift crew necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.

i' y

)

il b

1

! 1 "j

,3 l

i.;

1 ie 1

4i.]

',}

d

1. Fire Brigade 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 /> la

,.l order to accommodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire

.j Brigade to within the minimum requirements.t Q

i

'_ )

4

!U Amendment No. 63, 75 190-e J

.m

y e

it_

g go I

_I lE c.:

_5I I

!Ej a

E

=e j

1 l8 8

g I

~

g i.

N en E

H I_

35, k

g l

j r'

t E

a I

2 g.

5 1

l

~

J S

=

5_

?s HE

[

ig l*l l!

l

~

~

e u

8 L

~

.T I

I

.__________l________.______.___

i g

I

. _ _ _ _.J II l"

gsa t

B

=

E

~~

$EE o

~

I l

I'!-n "l!

l d

aO O

z g F43 o

55 c

E G*

I

-.-r.. r,s.

s. a.

.:-~.

.w.,

.. s.

..... - --- - :n. n.,...:,;..,,.~__

.__.,-.-___y v

.s.. 3.

ll

\\ll

'I

..i. * *

• g,

,, t N

,ts It e

ts Ng pM e

oi o

pv 2

ya yT 9

gg uS gr 1

.k eO T

W gD gs t=

cW

]T yE F

gI tg=

gR a

gE W

E 5

0S F

I F

T A

e T

s S

r u

p e

tss i

F N

v F

O a

A t

T I

r S

T u

s AT ee*

eO e

s S

T E N C E R

N D T

t E

t A N W

n m M E R

f TN A

a A T

I H

O t

t 4

P p u l

E C

t R

S AM P R

U L2 AE AN1 L

O R

C c,

O I6 U

, S F

T N

I T

F AZE t

A e

T E

P S

I U

I E

S NC K

AI NA GF R

Y I

O TN

,4 i

O e l M

Y R

D A T

F E

E TM WT A

V WC I D IE GN T

I R I AR EWI S

S E

I M

D ERC C

DQ DEA I

d E

S CN S

o SMN SNM A

EAA t

t B

T tT A

g nSLM#

F C

o C

Et n.oEL f

tt C.

SsCIT Ts n,P.

N'.

8o O4R SRsA WN TS RtO uEvI APl W

FCT oTaMSl 1,

I",

IA tTtMWPT 58itI gII1e T

ELa tar

(

N

-,EE R

s IMufIEA TP I :r S

SfTHt a

LU FEOnOS AITs AS R

oPCSLS i

M O8oAEsI pts R

tf tCFOOs F7taVTS A

9nrtETMEE fe 21aefFWTSTn r

t ScA P

?AE RN O 8,N t S8.eeTTWTTRT s

eO m

I r

u S8tsSLT Es e

n N1sstAL9FTf r Lf g m 0

uenMASe rtrtI Ao EGE 5

mm gsCCst I Cm5E 3 a E m I t. e s T r RALIAI&A( As 7

g p a t g a g

1. • ee

+

ay

• S m

.o N

e N

8 s

, S t

4 t

=

O o

0s s

n S

r s 83e 0

m TE M e

nT T

0 0

, Mo A O I

r I 8

f 1

B6a 0 t I S m

uB 5 e P

8 a

. 0 A L A d

9 s

. a e

. P r

I B 0

g

. s R W n

W u

wS r

r s

O O

B W e

A m

A I'

ltlt

VYNPS 6.2 REVIEW A7D AUDIT Organizational units for the review and audit of plant operations shall be constituted and have the r?sponsibilities and authorities outlined below:

A.

Plant Operations Review Committee 1.

Membership a.

Chairman: Plant Manager b.

Vic e-Cha irman: Operations Superintendent c.

Vice-Chairman: Technical Services Superintendent i

d.

Vic e-Cha irman: Maintencnce Superintendent Engineering Support Supervisor e.

f.

Operations Supervisor I

g.

Maintenance Supervisor h.

Reactor and Computer Supervi,sor i,

Chemistry and Health Physic Su pe rvisor j.

Instrument and Control Supervisor k.

Health Physicist 2.

Qualifications g

The qualifications of the regular members of the Plant Operations Review Committee with regard to the combined experience and technical specialties of the individual members shall be maintained at a level at least equal to or higher than as described in Specification 6.1.

3.

Meeting Frequency: Monthly, and as required, on call of the Diairman.

4.

Quorum:' Chairman or Vice-Chairman plus four members or their designated alternates.

NOTE: For purposes of satisfying a quorum, a Vice-Chairman may be tonsidered a member providing that Vice-Chairman is not presiding over the meeting.

Amendmer.t No. 56, 75 I'0 t

p; I.

. ;y l'

C.. Procedures prepared for A and B above shall be reviewed and approved by the Plant Manag2r, or his depigne 3

4 i

]

the Manager of Operations.

1 n

Temporary changes to procedures described in SpecificCtion 6.5.A above which do not change the intent of the such E. D. original procedure, may ibe made with the concurrence of two individuals ho s

i designee.

~

Temporary changes to procedures described in Specification 6.5.8 may be made with the concurrence of an 4

i M

E.

individual holding a senior operator license and the health physicist on duty.

[

Practice of site evacuation exercises shall be conducted annually, following emergency procedur l

F.

a j

a check c ca==anications with of f-site support groups.

Tests th leakage and/or Licensed radioactive sealed sources sh 11 be leak tested for contamination.

contamination shall be performed by the licensee or by other persons specifically authorised by the Commissio C.

or an agreement State as follows:

i Each licensed sealed source except startup sources previously subjected to core flux, containing radioact materials, other than ifydrogen 3, with half-life greater than thirty days and in any form, other than gas, 1.

shall be tested for leakage and/or contaalpation at intervals not to exceed six months.

The periodic leak test required does not apply to sealed sources that are stored and are not being used.

D e sources exempted from this test shall be tested for leakage prior to any use or transfer to another user 2.

In the absence of I

unless they have been leak tested within six months prior to the date of use or transfer.

a certificate from a' transferer indicating that a leak test,has been made within six months prior to the transfer, sealed sources shall not be put into use until tested.

j Each sealed startup' source shall be tested within 31 days prior to being subjected to core flux and 3.

following~ repair or maintenance to the source.

1 The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the I

If the test reveals the presence of 0.005 microcurie or more of removable contamination, it shall

)'

test sample.

inunediately be withdrawn from use, decontaminated, and repaired, or be disposed of in accordance with Commission l

j regylations.

Notwithstanding the periodic leak tests'. required by this Technical specification, any licensed sealed source is

,l j

exempt from such. leak test when the source contains 100 microcuries or less of beta and/or gamma emitting

,l

- i l

material or 5 microcuries or less of alpha emitting material.

]*

A special Report shall be prepared and submitted to the Commission within 90 days if source leakage tests reveel'l i

l j

the presence oft.0.005 microcuries of removable c >ntamination.

20s

..