ML20023B811

From kanterella
Revision as of 01:10, 27 February 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed Tech Spec Changes,Clarifying Wording of Surveillance Requirements for Sealed Sources Each Time Reactor Startup Occurs
ML20023B811
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 04/27/1983
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20023B807 List:
References
NUDOCS 8305060405
Download: ML20023B811 (7)


Text

_ _ _ _

NI'TACBeir 1 h3~ N

,m

,Y PLANT SYSTEMS 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of > 0.005 microcuries of removable contamination.

APPLICABILITY: At all times.

ACTION:

a. Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:
1. Either decontaminated and repaired, or
2. Disposed of in accordance with Cc= mission Regulations.

(~N L./'

b. The provisions of Specifications 3.0.3 and 2.0.4 are not appli-cable.

SURVEILLANCE REOUIREMENTS 4.7 9.1.1 Test Recuirements - Each sealed source shall be tested for leakage and/cr contamina: Ton by:

a. The licensee, or
b. Other persons specifically authericed by the Commission or an Agreement State.

l De test methed shall have a detection sensitivity of at least D. DOS--r^-

tehydamn microcuries per test sample. i//gg i

.as (w

4.7.9.1.2 Test Frecuencies - Each category of sealed sourcesp tested t tne frequencies cescribed below. A

a. Sources in use kxcluding st+r4tte-sett ~:-es ;nd 'i--kn d:tC t:r; preficuslt s uW4ed-to-eerc el t;x ) - At least once per six

() 8305060405 830427 montns for all sealec sources ccntaining radioactive material:

PDR ADOCK 05000317 P PDR CALVERT CLIFFS-UNIT 1 3/4 7-63 M & rr Ib l

x _

J[f 93-46 ATTAC995ff l'(Cont'd) p ..

M .

PLANT SYSTEMS h. '

v.

SURVEILLANCE REOUIREMENTS (Cokinued) 3, n

1. With a half-life! greater than 30 days (excluding Hydrogen 3),and 4'
2. In any form othe/ than gas.

T~

b. Stored sources not in use - Each sealed source and fission .

cetector shall be tested prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.

c. Startuo sources and fission detectors - Each sealed startup days source prior to being and fission subjected detector to core shall begsgggny%

flux cau a ro.6vw n3 pair or y

maintenance to the source or detector.

4.7.9.1.3 Reoorts - A report shall be prepared and submitted to the a Comission on an annual basis if sealed source or fission detector W leakage tests reveal the presence of > 0.005 microcuries of removable contamination.

O CALVERT CLIFFS-UNIT 1 3/4 7-64 j mod-id #c.

_ --__ _ _ _ - - - . - 1

~ ..

93-%

'. ATTACIMNr 1 (Cont!d)

' PLANT SYSTEMS

() 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING C0"DITICN FOR CPEP.ATION 3.7.9.'l Each sealed source containing radioactive material either in excess of 100 micrecuries of beta and/or gamma emitting material or 5 microcuries of Eipba emitting material snail be free of > 0.005 microcuries of removable centamination.

APPLICABILITY: At all times.

ACTION:

a. Each sealed source with removable centamination in excess of the above limit snall be immediately withdrawn from use and:

? 1. Either deconta=inated and reDaired, or

2. Disposed of in accorcance with Ccmmission Regulaticns.

Il i b. The provisions of Specifica:icns 2.0.3 and 3.0.4 are not appli-('l -

cable.

v l

i ~^

SU RV _ n_'-~* ", u". er -e-"7.R

. ..".';TC 3

4 i

! 4.7.9.1.1 Test Recuirements - Each sealed scurce snall be tested for I leakace anc/or contamina:1cn by:

i

! a. The licensee, or

.e l b. Other persens s;ecifically authcriced by the Ccemissica or an j Agreemen: State.

The test method shall have a detec:icn sensitivity of at least 0.005 microcuries per :es: sampic. em I

(e.caem stcrhp w, l' 4.7.9.1.2 Tes: Frecuencies_- Each catecerv cf sealed scurce2 rnTTT' YeT c d 6sh tested at :ne frecuencies cescrl:ed below.' , /?EEuus s5Jel*"-s g[.j>j

a. Scurces in use n =-c -- ~ct:rtr- - - :: :nd ::::icr :; -

crem;c;;; tur-c"-="  ::re =  ; c ieast once per s x mon:ns for ali seaiec sources cen airing radioactive material:

O a

CAL'/ERT CLIFFS-UNIT 2 2/c 7-55 ,

Hverinut No.

_L $3-%

ATTAClearr 1 (Cont'd)

G*(

t -

7 -,

b-( l PLANT SYSTEMS .

SURVEILLANCE REOUIREMENTS (Continued) e-i

1. With a half-life $ greater than 30 days (excluding Hydrogen.

3),and -

2. In any form other than gas.
b. Stored sources not in use_ - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested:within the previous six months.. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
c. Startup sources and fission detectors - Each sealed startup source and fission detector shall be tagagghjg31 ndays g prior to being subjected to core fluxfEno roi sawmg repair or maintenance to the source or detector.

4.7.9.1.3 Reoorts - A report shall be prepared and submitted to the Comission on an annual basis if sealed source or fission detector leakage tests reveal the presence of > 0.005 microcuries of removable contamination.

.- s CALVERT CLIFFS-UNIT 2

.'3N'7-64 Med S.

..L:h:

i O O O '.

TABLE 3.7-4 .

)

"J SAFETY RELATED llYDRAULIC SNUBBERS

  • 4 r"-

E SNUBBER SYSTEM SNUBBER INSTALLED ACCESS 10LE OR HIGli RADIATION ESPECIALLY DIFFICULT E ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE NO.

E (A or 1) (Yes or No) (Yes or Ho) {

A No No 2 1-36-1 SUCTION #11 AUX. FEED PUMP 12' A No No 1-36-1A SUCTION #11 AUX. FEED PUMP 12'

@ f s

g8 n  ; -

m

~

w J.,

6e M O-4 RE550RIZER-S AMPLE-LINES-38' I Yes = l I Yes No i 1-38-S PRESSURIZER SAMPLE LINES 24'-

I Yes No 1-38-6 PRESSURIZER SAMPLE LlHES 37' i

((

A No No 1-24-1 DIESEL GENERATOS #12 EXilAUST 92' h '

A No No

" l-24-2 DIESEL GENERATOR #11 EXilAUST 92'

=

M w o 8 Ld LG

  • j

F 1

b ShnA We NJ1 ear her l

! [ ,

I

. Plant Cacd up,g p gs CDemtlans

--- ..--....--- &cety m.g ..g g g,m F. view w.7;gg

  • Ctraittu sarace,

,------ ,------ ,------ 7.----- ,

e i e i i , e e a i

e e SK W J4:ir MII"8 M-C#W id$

& CEtrols TE tr#Jacrt 4 Ac'.e2 t $1.

~

arut

%dificaticr.s dif$,.

Irancerir.

helear d$ $$

Mtf AssJarae Miew femarity

  1. 4:1-

- [7

'~~

~L U g,,,g' YM #

-- T#'"

W  ;

I I I i i i i x

"aJ' Milj'" R*J" ,'2 EEcr Eh- mmca

%ts C.m w

satt m

_ _ 22S$1 u .

i uc Seract Ccr.trcl

=

Stedanteel m- g%

4 enter h?

x IEGEND: RO - Reactor Operator License h Tg SRO - Senior Reactor Operator Q

    • ^*" . License pj

'Onsite Responsibility for Fire 4 Protection Pmgram w r :=

@6 TEM Figum 6.2.2 Organization Chart (Two Unit Operation) - Calvert Cliffs Nuclear Power Plant Baltimom Gas and Electric Conpany . s l

i

g, ATTACIfbh' 4 y- ,.

f-ADMINISTRATIVE CONTROLS p

. 6.3 FACILITY STAFF QUALIFICATIONS ,

)

I 6.3.1 Each member of the facility staff shall meet or exceed the minimum L qualifications of ANSI N18.1-1971 for 'ccmparable positions, except for the f Radiation Safety Engineer who shall meet or exceed the qualifications of k Regulatory Guide 1.8 September 1975, arid (2) the Shift Technical Advisor who

~

shall have a Bachelor'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.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor - Training and Technical Services for the Nuclear Power Department and the General Supervisor for the Production Maintenance Department and shall meet or exceed the requirements and recc=mendations of Section 5.5 of ANSI N18.1-1971 and Appendix " A" of 10 CFR Par: 55, as applicable.

6.4.2 A-training program for the Fire Brigade shall be maintained under the direction of the General Supervisor - Training and Technical Services and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975. _

6.5 REVIDI AND AUDIT

6. 5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)

FUNCTION 6.5.1.1 The POSRC shall function to advise the Plant Superintendent on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The POSRC shall *ie ccaposed of the:

Chairman: Plant Superintendent Member: General Supervisor - Operations Member: General Supervisor - Electrical and Centrols Member: General Supervisor - Chemistry Member: Principal Engineer - Plant Engineering Nuclear

[ Member: General Supervisor - Maintenance and Modifications l

Member: Principal EnE,ineer - Incore Fuel FanaEement Member: General Supervisor - Radiation Safety Member: General Supervisor - Training and Technical Services l

ALTERNATES 1

l 6 . 5 .'l . 3 All alternate members shall be appointed in writing by the POSRC l

Chairman to serve on a temporary basis; however, no more tnan two alternates l shall participate as voting members in POSRC activities at any one time.

l CALVERT CLIFFS 6-6