ML20092A402

Forwards Responses to Listed Outstanding SER Confirmatory Issues Discussed at Meeting W/Radiological Assessment Branch

ML20092A402
Person / Time
Site:	Beaver Valley
Issue date:	06/13/1984
From:	Woolever E DUQUESNE LIGHT CO.
To:	Knighton G Office of Nuclear Reactor Regulation
References
2NRC-4-078, 2NRC-4-78, NUDOCS 8406190191
Download: ML20092A402 (29)

Text

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2NRC-4-078

= (412)787 - 5141 (412) 923 -1960 Telecopy (412) 787-2629 Nuclear Construction Division June 13, 1984 Robinson Plaza, Building 2. Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. George W. Knighton, Chie f Licensing Branch 3 Of fice of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Outstanding / Confirmatory Issue Response Gentlemen:

This le t ter fo rward s res pons es to the issues listed below, diich were discussed at a meeting with the Radio logice' As ses sme nt Branch .

Duquesne Light Company plans to incorporate the res po ns es as indic a ted in each attachment into FSAR Amendment 8. The following items are attached:

Attachment 1: Response to Confirmatory Issue 12 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report At tachment 2: Response to Confirmatory Issue 13 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report At t achment 3: Response ta Confirmatory Issue 14 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Attachment 4: Response to Confirmatory Issue 15 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report At tachment 5: Response to Confirmatory Issue 16 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Attachment 6: Res ponse to Out standing Issue 95 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Att achment 7: Res pons e to Outstanding Issue 96 of the Beaver Valley Power Station Unit No. 2 Draft Safety Evaluation Report

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8406190191 840613 PDR ADOCK 05000412 g t

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. United Stctes Nuclear R:gulatory Commission Mr. Georga W. Knighton, Chief Page 2 At tachment 8: Res pons e to Out standing Issue 97 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Attachment 9: Technical Specifications DUQUESNE LIGHT COMPANY By . . [

E. J M Wo'olever Vice President GLB/wjs At tachment cc: Mr. H. R. Denton, Director NRR (w/a)

Mr. D. - Eisenhut , Director Division of Licensig (w/a)

Mr. G. Walton, NRC Resident Inspector (w/a)

Mr. M. Licitra, Project Manager (w/a)

Ms. M. Ley, Project Manager (w/a)

COMMONWEALTH OF. PENNSYLVANIA )

) SS:

COUNTY OF ALLEGHENY )'

On this /8 k day of y, _, /f/ , be fo r e me ,

a Notary Public in and fo r said Commonwe alt h and County, pe rsonal ly appeared E. J. Woolever, who being duly sworn, deposed and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execut e and file the foregoing Submit t al on behalf of said Company, and (3) the s t ateme nt s set fo rt h in the Submittal are true and correct to the best of his knowledge, f Nu ) 1 Not ary Pub lic ANITA ELAINE REITER, NOTARY PUBLIC ROBINSON TOWNSHIP, ALLEGHENY COUNTY MY COMMISSION EXPlRES OCTOBER 20,1986

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ATTACHMENT 1 Response to Confirmatory Issue 12 of the j Beaver Valley Power Station Unit No. 2  !

Draf t Safety Evaluation Report i

Draft SER Section 12.2.1: By-product, Source, and Special Nuclear Material Description (Excerpt)

A description of by product, source and special nuclear material of cons ideration in plant shielding design will be provided seven to nine months before fuel loading (Q471.14).

Response

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I r l The need for procurement of sources beyond those now in use at BVPS-1 has not been fully determined. Seven to nine months prior to fuel load- ,

ing, a description of by product , source , and special nuclear material  !

that requires shielding design considerations will be provided. A list-  !

ing of isotope, quantity, form, and use of all special nuclear material exceeding 100 millicuries and requiring shielding design considerations l will also be provided. This information will be included in the FSAR in  !

accordance with Regulatory Guide 1.70, Revision 2..

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- i ATTACHMENT 2 Response to Confirmatory Issue 13 of the Beaver Valley Power Station Unit No. 2  ;

Draft Safety Evaluation Report j Draf t SER Section 12.3.1: Verification that Cobalt use in Primary System has f been Minimized (Excerpt) l t

i The ap plic ant 's corrosion product control fe atur es are cons istent with i the guidance of Regulatory Guide 8.8 and are ac cept able , although con-firmation that the basic plant design reflects an ef fort to minimize the ,

cobalt content of materials used in primary systems is needed (Q471.10).

Response

l FSAR Section 12.3 and the response to Question 471.10 will be revised as  !

shown on the attached pages.  ;

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. s BVPS-2 FSAR ,

Remote handling equipment.is provided for removing filters ,

from the filter vessels and for placing them into shipping (,!j containers. Contact operations in high dose rate areas are ,

minimized.  !

The solid waste system is essentially a remotely operated  ;

system. Operations are conducted remotely or manually after '

the waste source has been shielded.  ;

stations for potentially radioactive valves are, in general, l arranged either in shielded cubicles away from the equipment i 1

served and/or are provided with reach rods. The  ;

demineralizer and filter valves are in cubicles below and adjacent to the vessels and are also provided with reach j rods.  !

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17. All features for radiation control are designed to  !

accommodate maximum expected failures such as fuel element i cladding failures and steam generator tube leaks. l l

Design features such as shielding- and radiation zones i accommodate clad defects for 1 percent failed fuel and primary to secondary steam generator tube leaks of 144 gal / day. ,

18. Sampling. sites are located. so exposures will be ALARA during such routine operations, as sampling off-gas, primary ,".. '

coolant, and liquid waste. ' '

I A sampling room is provided for the remote taking of routine [

-samples from points in the ' reactor and auxiliary systems with the- exception of the samples from the evaporators. '

Sample points for the evaporators are provided with a sample sink and ventilation hood, splash screen, and valves located

' outside the splash screen. The samples are provided with a  :

recirculation path behind the shield wall at the sample sink with reach rods for the operator. A shielded sample station is also provided. for solid waste streams (for example,

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evaporator bottoms, resins and sludges).  ;

19. Redundancy of equipment is utilized in the plant design to - ,

facilitate ALARA by allowing longer holdup time .between .

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scheduled fluid processing r.ad by reducing the urgency for accelerated equipment repair. Redundant radwaste ,

solidification drum inspection / labeling stations permit i processing more drums in shorter periods of time to reduce ,

individual exposure to radioactive sources.

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12.3-8 May 1983 Amendment i t:

BUPS-2 FSAR Two safeguards recombiner area monitors are provided outside the cubicles in which the post-DBA hydrogen recombiners are located. ,

a A list of area radiation monitors and their locations, sensitivities, and ranges is presented in Table 12.3-10. The sensitivity of each L

monitor is the lower value of the monitored range.

12.3.5 References for Section 12.3 Stone & Webster Engineering Corporation (SWEC) 1975. Radiation Shielding Design and Analysis Approach for Light Water Reactor Plants. Topical Report RP-8A, Boston Mass.

SWEC 1981a. QADMOD - Point Kernel Gamma Transport. NU-137.

SWEC 1981b. ANISND - A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering. NU-146. T SWEC 1981s.. COHORT 2 - Monte Carlo Radiation Environment Aitalysis.

NU-157.

SWEC 1982. GAMTRAN1 - Gamma Transport by Point Kernr1 Technique.

NU-003.

U.S. Nuclear Regulatory Commission 1980. Clarification of TMI Action

, Plan Requirements. NUREG-0737. ,

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i Amendment 3 12.3-32 October 1983

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INSERT 1

20. Materials

'- Equipment specifications for component s in the nuc le ar steam supply

-system contain specific limitations on the cobalt impurity content of the base metal as given in Table 12.3-11 thereby controlling the poten-tial -for production of radioactive cobalt-60 from the base metal impur-ity cobalt-59. The estimated surf ace area of material in contact with i the reactor coolant is given in Tsbie 12.3-11. The use of hard facing material with cobalt content such as stellite is limited to applications where its use is necessary for reliability considerations. Table 12.3-13 shows the es timated tot al surface area of stellite in the nucle ar stema supply sys tem. Nickel based alloys in the nuclear steam supply l

system (cobalt-58 is produced fra activation of the base metal nickel-

58) are similarly used only when component reliability may be compro-mised by the use of other materials. The major use of nickel based alloys in the nuclear steam supply system is the inconel stema generator tubes. The surface area in contact with the reactor coolant sys tem is given in Table 12.3-12. Fram Tables 12.3-12 and 12.3-13, it can be seen that. the inconel surface is the predominate area in contact with the reactor . coolant systen and. that the stellite area is minimal. A further discussion of material considerations is given in Westinghouse (1977).

I INSERT 2 i

Westinghouse 1977. " Design, inspection, operation, and maintenance as pect s of the Westinghouse NSSS to maintain occupational radiation exposures as low as reasonably achievable," WCAP 8872, April 1977.

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. T ABLE 12.3-il EGU!PMENT SPECIFICATION LIMITS FOR COSALT iMPUHf1Y LEVELS Maximum ,

Camponent Materlot" Weloht Purcant Cobol,t, Reactor interneels (nnnactive region) 55' U.20 Reactor internals (w:tiva region) 55 0.12 -

Reector vessel clad SS 0.20 -

Reactor cuolent piping 55 -

0.70 Reector internal botting (natcrial SS , 0.25 Remetnr enoient pumpe SS 0.20 55 0.20 Pressurizer Auxillery host exchanger surfnewe vaposed to reactor coolant SS . 0.20 Stasm generatore Incunal 0.10 - ,

Fuel (mmactive region) 55 0.12 Fust(active ruginn) SS 0.08 Fuel Inconel 0.13 Zircoloy 0.007 Fuel

'55. Staininas steel 5

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55* 4276 Remstor vagoni elarf SS 2190 Remeter coolant plpirwJ 55 775G ,

Rosetor internal 14ultitwJ material .55 Negligihte

• Reactor coolant pumpe 55 -

Negligtble Aumillary twmL cachassler surfaces facef,t, l: Negllgibin Stoom generotore ,

inconel 1.90 x 105 fuel (pannetive region) $$ 2000

+ Fuel (active region) $$ 3600 Fuel Inconel 7.A0 r 10)

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t BUPS-2 FSAR NRC I.etter: August 31, 1983 i

I Question 471.10 Discuss how material selection and water chemistry control will be  !

utilized at BVPS-2 to reduce the production, distribution, and i retention of activation products.

i Responses Material, selection for components in the reactor coolant system is l discussed in Sections 4.5, 5.2.3.1, 5.3.1, 5.4.2.1, and 5.4.3. Water chemistry control and reactor coolant purification are discussed in i Sections 5.2.3.2.1 and 9.3.4.

F Use of corrosion-resistant materials, implementation of water i chemistry monitoring procedures to control the oxygen content and ,

impurities in the reactor coolant system, and continuous purification  !

of the reactor coolant letdown through cleanup systems reduces the production and retention of activated solid corrosion products. The  ;

chemical and volume control system is designed to provide an effective means for removing these corrosion products from the ,

i primary coolant, as discussed in Section 9.3.4. i REFE4% AEVt6ffD sac.wed 2.. & , i, t. F6 A 41:se.ussied bv c.o&4t.T cont w r na _.

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i Q471.10-1 October 1983 Amendment 3

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ATTACHMENT 3 Response to Confirmatory Issue 14 of the Beaver Valley Power Station Unit No. 2

Draf t Safety Evaluation Report T

Draft SER Section 12.3.4.1: Cont ainment High-Range Radiation Monito rs (Excerpt) l i

Additional information regarding cont airunent high-range-radiat ion monitors (NUREG-0737, Item II.F 1(3]) needed to complete the review will  ;

be provided by the applicant (Q471.14). j k

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Response

FS AR Table 12.3-10 has been revised to provide the missing information >

related to cont ainment high-range radiation monitors as shown on the ,

attached page. the res ponse to ques tion 471.14 will be revised accordingly.

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,g TABLE 12.3-10 AREA RADIATION MONITOR LOCATIONS AND RANGES Sensitivity and Detector Location Range * (mrem /hr)

Reactor containment area, low range 1-105 Outside personnel hatch area 1-107

) Reactor in-containment area, high range 103-1018 Manipulator crane 1-105 In-core instrumentation area 1-105 Decontamination area -

0.1-104 .

New' fuel storage area 0.1-104 Fuel pit bridge 0.1-104 Auxiliary building 0.1-10+

,6, Sample room 0.1-10+-

Waste handling area s 0.1-104 Condensate polishing area 0.1-104 Control room 10-2 103 l Safeguards recombiner area 1-105 NOTE: ,

• Sensitivity is equal to the lower value of th range.

Amendment 3 1 of 1 October 1983 w

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ATTACHMENT 4 \

r Response to Confirmatory Issue 15 of the Beaver Valley Power Station Unit No. 2 i Draft Safety Evaluation Report i

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Draft SER Section 12.3.4.2: Airborne Radioactivity Monitors (Excerpt) [t I

The applicant will ins tall airborne radioactivity monitoring sys tass  !*

(RMS) in work areas dere there is a potential for airborne radioactiv-icy. Visual and audible alarms are provided in the main control roam for these monito rs . The licensee should verify that the RMS airborne monito rs have the capability to de tect 10 mye hours of part iculate and iodine radioactivity in any compartment that has a possibility of con- -

taining airborne radioactivity and that may be occupied by personnel. l The applicant will provide portable continuous air sanitors den needed  !

to monitor air in areas not provided with fixed airborne radioactivity monito rs . Airborne Radioactivity monitors will be calibrated at regular time intervals as required in Technical Specifications. j i

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i FSAR 12.3.4.1 provides the requested information. A calculation has been performed to confirm the capability to detect 10 spc hours.  ;

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ATTACHMENT 5 Response to Confirmatory Issue 16 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Draft SER Section 12.5.3: Quality Assurance Program Requirements (Excerpt)

Verification that quality as surance requirement s related to radiation protection have been implemented at Beaver Valley 2 in accordance with Regulatory Guide 1.33, " Quality Assurance Program Requirements," should be provided.

Response

FSAR 12.5.3 will be revised as shown on the attached page.

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BVPS-2 FSAR The. radiological limits, controls, and policies as described in the l Id Radeon Manual will be consistent and in compliance with the N/

/3 recommendations and requirements of applicable federal and state l

.) regulatory agencies. In accordance with both company and station 0 and o administrative policies, compliance with the controls. limits, E k requirements of the Radeon Manual will be mandatory.

o,e g 3 The Radeon Manual will be supplemented by other work procedures to g 4 => assure that abnormal or unique work practices and/or operations are y $ conducted in accordance with the Radeon Program. This will ensure ,

oc N standards and limits specified therein ~

are carefully and conservatively followed so that radiation exposures, contamination -

g7 y (surface or airborne) levels, and radioactive waste volumes are ht yE maintained as low .as reasonably achievable and consistent with established requirements.

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YgQ The Radeon Manual and other work procedures will contain information on external radiation protection, respiratory protection,, protective y g. O y y clothing, etc; including detailed specifications, qualifications, ,

4 '.1 a precautions, performance limits, and/or controls and any other l 9y 4 information, personnel exposure.

instructions, or guidelines required to minimize  !

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2g The Radcon Program, as presented in the Radeon Manual, will be  !

$44 e developed in accordance with 10 CFR 20 and other applicable federal 33 g,, & _and state regulations.smRevisions in applicable regulations that are T 3 f F adopted and published in the Federal Register, or are issued in the NRC Regulatory Guides will be evaluated by the Nuclear Division g*p

• Staff, as well as the station staff. If warranted, the Radeon Manual-sl! 4 be revised to be consistent. with the revised rules and d $ .$ will

.t practices.

The Radeon Program and its implementation will be audited periodically by qualified person (s), who are not assigned to the station, to ensure the program is in compliance with existing requirements. Audit findings.will be reported to mangement for their

-information and 'ppropriate action.

12.5.3.1 ALARA Physical and administrative controls will be instituted to assure DLC's philosophy of maintaining personnel exposures as low as reasonably achievable (ALARA) is implemented.

12.5.3.1.1 Physical and Administrative Controls Operation of the plant, as well as certain maintenance and repair tasks, may require access to and work in all areas of the plant. ,

This includes areas defined by 10 CFR 20, as radiation areas and high Amendment i 12.5-10 May 1983 1

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ATTACHMENT 6 Response to Outstanding Issue 95 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report Draft SER Section 12.3.4.1: Exemption to 10CFR70. 24(a) and Description of Alternative to Required Criticality Monitors (Excerpt)

The applicant has provided area radiation monitors around the fuel stor-age areas . These do not meet the particular requirements of 10CPR70.24 and the related guidance of Regulatory Guide 8.12 " Criticality Accident Al re Systems:" however, the ap plicant will file for an exemption frcut 10CFR70.24(b) by September 1984 The ap plicant must still provide a discussion of the proposed alternative monitoring methods as reques ted by the staf f (Q471.3).

Response

The response to Question 471.3 will be revised as shown on the attached page.

f BVPS-2 FSAR NRC Letter: August 31, 1983 Question 471.3 DLC has indicated in Table 1.9-2 that'an application for an exemption in from the installation of the criticality monitor required accordance with 10 CFR Part 70.24(b) and Regulatory Guide 8.12 will be filed with the NRC. Provide a commitment date for this action and describe the specific alternative methods to be used in lieu of the required monitors.

Responset The application for exemption will be formally filed as part of the application for a special nuclear materials license which is to be submitted in September 1984. Alternative methods which preclude the need for a criticality monitor include administrative controls for the movement offuelDppropriatedesignoffuelstoragefacilities.,

(to prevane critica nty. and plant security controlsf TH ESC 39tTEAurTIMS

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I ATTACIDENT 7 Response to Outstanding Issue 96 of the Beaver Valley Power Station Unit No. 2 j Draf t Safety Evaluat on Report  !

l Draft SER Section 12.5.2: Types, Nude rs , and Specifications fo r Port able {

and Laboratory HP Instruments (Excerpt) i The number and type s of survey equipment , the sensitivity and range , and i details of calibration are needed to complete the staf f's review in this  !

area, and the applicant has cosusitted to provide the information. [

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Response: ,

Figure 1 (attached) provides an example of the general type and approxi- l mate quantity of tortable and laboratory health physics equipment avail-able at BVPS-1 as of April 19 , 19 84. This table demons trates that i Duquesne Light Company is fully cognisant of the types and nudes of  !

equipment required to conduct an ef fective health physics program.

Figure 2 ( attached) provides - tabulation of the general types of po rt able and laboratory equipment dich are expected to be employed for ,

radiological monitoring at BVPS-2. l l

The standard review plan provides no quantitative accept ance criteria  ;

for determining the necessary types and quantities of ins trument ation required to support a successful health physics program. With continual  ;

improvement s in technology, industry practices , and regulatory require- j me nt s , it is not possible to provide specific acceptance criteria, nor  :

is it appropriate to provide a listing of the types and quantities in the FSAR.

i Duquesne Light Company will maintain health physica equipment required  :

l to perform radiation and contamination surveys, airborne radioactivity

• monitoring and sampling, area radiation monitoring, and personnel moni- l l

toring during normal operation, anticipated operational occurrences, and l accident conditiona at BVPS-2: The types and quantities of equipment to i i

l be employed at BVPS-2 will be continually changing based upon experience

! In order to improve the efficiency and ef fset iveness of the he alth physics program. l I

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< =2 n z 3l uas 14 si ,

i I, !

l  ! ib=

l O44t.a g =m! .ll . _ . -

. n 4 .ar 4 4 444 4 4 U

1 e

m W

U = g - e =

w "w 3 1 g 5 5 -

8 g 3 ge "8 : -

si a

3 a

!. 5 E

a o

s- s=

a a a a a 4 -

E E

,'.~ La

~ ~ .

I 5

= -

5 2

5 m r a 5 m 3 e c

- - =

N W N N j

l

- e s 5 a g g i

i s a .

l  :

x, l,  !

l l ll l E

s k $ $ l I a e -

g = .

_ a I- 5 '

• 4 V '

c . - I A I -

3

== --

a

R gs: 23 af _3-l u l

Eg a 1 E-

=.8

= a

= ., l

m. g [*

=e

4 . t= a

~

s  :

e, & a g .f . .:_A 1 a ga a -

'3  : d

• a y ~a a I - .s- as t g 5 d i , - .- . . a -

5 d I - d - 4 4 5 4 0 l

c "

• S 3

=

5.. 5 2 y h

• "n 1

= -

• I a" n a

s i

< n=

.is_a g t 2 =

se -

= =

a w - 44. I N . a. a. e. a. .

! 4 M 4 . . J . . . .

5 I

- e. y Y b Y $ t

=

s

~

E -

• 0 E 5 g 5 g W a 5

, g : "

= ,

~

" n E

• E [

Ia g g

~

5 - - -

M

'I E

~

.l : .* 55 -= s s s wa -- --

'~

g E E E ET I ej "I t av s 5

- E lE -

• W W . 35

• l

-y _ m 9

o e e

O Y

E .

/d s

= . a

!,  !. !. ] . . - 2 - -

3 5

~

e 5 2 3 E J

!= .

l

~

3 -E 2 I

2 82E la 3 E

~

$ $ 5 g J N N e e

_ s e .

2 --

Er a

e n -(( -

, g = l=B w a 2 0 -0 E s 0= 0= Ig j g 5 I

a

~ '

a g =

I I a IEE c

E $$

g I .

] g !

I w - - E - - -

g,

=  ! ! 11 5  ! a

! ! i l s! I t-n l 5 - .

Y s} 38 .  !

M E *2 a

E:

t . t G I ' t M WW i

=

5 2 0 g g C 3 y =W .!

- - *3 - - ., so .

I 3 E E  : IT

. I ,

I ,

a .. -

s - a m

I g

i d d

• g E I E E E Ik ,

4 l ,

l l

._ M . M . M M, . -w---w---..

_ __ _ _ ~ _

PORTADLE SURVET INSTRtMENTS TYPE METER RANCE M i SEN5tpylTfjgFLClJ(lCT c,,.-ce 0-50.000 CrH Sr-90 Y-90(Eg3g.54-2.ZMev) 451 G-M PANCAKE (FRISKER) 0-60.000 CPM Tc-99(EnAx.29MeV) 30%

C-14 (Eggg.15Mev)10%

Co-60 5000 CPM /mR/hr Cs-137 3500 CPM /mR/hr 0-200 mR/hr WITil!N +20% 40 KcV-1.25 MeV G-M LOW RANGE Cs-131 1200 CPM /mR/hr 0-20 R/hr Co-6019 CPM /mR/hr G-M HIGH RANGE Cs-13712 CPM /mR/hr PROSE: 0-200 mR/hr Cs-137 1200 CPM /mR/hr G-M CUM 8tMAfl0N INTERNAL: 0-2 R/hr Cs-131 100 CPM /mR/hr 0-1000 R/hr 80' kev-200 kev t15%

G-M EXTEN01BLE 0.2 MeV-2 MeV t101 LOW RANGE 0 200 mR/hr 1200 CPM /mR/hr G-M PORTADLE

. M10 RANGE 0-200 R/hr 1200 CPM /mR/hr HIGH RANGE O-10000 R/hr 60 kev-l .3 MeV .

0-5 R/he 7:15% 12 kev-1.3MeV IGN CHAM 8ERS Sr-90. T-90 75% AT 40 cm WINDOW OPEN 8% e.T 40 cm SLIDE CLOSED 0-50 R/hr y tl5% 12Kef-1.3MeV ION CHN1SER$ Sr-90. Y 90 75% AT 40 cm SL10E OprH 8T AT 40 cm SLIOC CLOSED 10N CHAM 8ER 0-1.999 R/he

• 0-199.9 R/hr 60 kev-1.3 MeV t201 -

CITEN0!BLE 0-19.990 R/hr i

0 1

O' 10.000 R/hr

• '60 kev-1,3 MeV 220%

ION CHAM 8ER COUNT RATE MODE: Pu-239 9 CPM /DPM/cm a ALPHA SCINTILLATION ,

0-10.000 CIW SCALER MODE:

6 OtGIT 0-500.000 CPM 50% OF 2 o GEOMETRY FROM 50 cm ALPHA GAS FL0u

=

(Pu-239)

HEUTRON COUNTER 0.2-2G .fs/wr 109 CPM /aree/he .

.LA80RATORT INSTRtmENTS DETECit0N MINIMLM DETECTARLE 3 .

T7PE ACTlvITY (W, fMi .

SINGLE-CHANNEL 6 Dialf SCALER 6.7 a 10-t e vC1/cc (t-131)

ANALYZER , FOR 20 FTs SAMPLE MULit-CHANNEL 1.6 a 107 CPS I a 10*? uCl/cc (Co-60)

ANALYZER FOR 30 MIN. C00fif CAS FLOW PROP 0Rit0 MAL 6 O! GIT SCALER 1.5 DPM ($r-90. Y-90)

COUNTER 6 O! GIT SCALER 7.0 x 10*7 pCl/ml (Co-60)

N4t (T1)

GM 6 OtG1T SCALER A8 OPM (Tc-99)

ALPHA SCINTILLATION 6 O!Gli SCALER 1.35 OPM (Pu-239)

{ f/ &IXLL ~

PORTA 8LE CONTINUOUS AIR MONITOR 5 TYPE RANGE [ n ;} EFFICIENC1 M J G-M 0-50.000 CPM 155, 2 r Sr-90. Y-9C I G-M U-100.000 CPM 50%. Zu Sr-90. T-90 '

i PORTABLE AIR SAMPLERS

• i TYPE FLOW ( m

+

GRA8-SAMPLERS CONSTANT: 2 CFM VARIA8LE: 0-3 CFM l HIGM V0 LIME 20-30 CFM 8REATHIM ZOK lZ LPM  ;

i RESPIRATORY PROTECTION EQUIPMENT  !

TYPE

• DESCRIPfl0N i

AIR-PURIFYIM - FULL FACEPIECE (MP)

. FULL FACEPIECE (PP)

ATMOSPH( K SUPPLYINE SCBA 'OPEN CIRCUIT (PO)

SC84 CLOSED CIRCulf (RO)  ;

L AIR-LIMIL FULL FACEPIECE IPO) ,

FULL FACEPIECE 1,CF)

I huus (GF)  !

I NP - NEGATIVE PRESSURE: PP - POSITIVE PRESSURES PO - PRESSURE DEMANO l RO - NECIRCULATING DEMAND', CF - CONSTANT FLOW l

f l

( Ilt #.O 1 c.wTh) l I

l l

i i r

6 i

r ATTACHMENT 8 Response to Outstanding Issue 97 of the Beaver Valley Power Station Unit No. 2 Draf t Safety Evaluation Report t

I Draft SER Section 12.5.3: Training /Retraiing for Health Physics Profes-sionals and Verification that Contractor Training Meets 10CFR19.12 (Excerpt) l Additional infc rmation regarding training for health phys ics profes- i sionals and requalification and retraining programs has been requested I (Q471.5), but the applicant has not provided a satis factory res ponse.

Additionally, the applicant should verify that contractor training is in l compliance with 10CFR19.12 and not merely task oriented. [

l P

. l Response: ,

Although no regulatory requirements exist for specific training or I retraining of health physics professionals, Duquesne Light Company does  ;

provide professional development trainirg for appropriate individuals to assure a proficient health physics staf f. This training is acccuplished thr ough participation in training progemas , seminars , or workshops .

I sponsored by various industry and profe'esional groups. Participation in l

these progress maintains the health physics staf f's level of knowledge  !

current with changes in the industry resulting from technological inno- i vations and development s as well as chose res ulting from ch arging l

regulatory requiresent s. Appropriate information obt ained through participation in such training may thou be incorporated as improvement s i in the health physics program. ,

i l

With regard to 10CFR19.12, all individuals working in or frequenting any portion of a res tricted area receive the ins truction delineated in 10CFR19.12.

! . i 1

l r i

I i

i

ATTACHMENT 9 Technical Specifications The at t ached draft technical specifications are provided in suppo rt of the following ste.tements found in the Draf t SER.

a. " Airborne radioact ive monitors will be calib rated at regular time intervals as required in technical specifications." (SER 12.3.4.2)

b. "In the technical specifications , the ROC should be confirmed to be a member of the station's onsite safety committee." (SER 12.5.1)

G

• ~ ~ ' ,- , - , - , - - - , , , , _ _ _ _ __,

.._ .x ..,m_ - __ -- -

4 e.

e Q .3 em O C O N 3 e O C C C O

MW e

=e C e O as *

• C

• e E 1 C .* e Z E E E e u=

2 C W 3 6

w' W

2 ,

4 e m

=6

==

W "s

> C' m M O 3 me = 4

@ e **  %

C e M e E 8 5 5 K E C es m w e$

t e= K =

• W ua

> e *=

W W fJ 3

e.

4 5

. e= q

==

3 E '

3 e O C .M 1/9 'A

== C U ett sn Ut 11 7

== e e 4 &J

== uu O

4 E .

es.

C l m t u.a C N @ 8 0 m a = **

e a tw e 4

• me em m a 3 S 7 @ @ e W **

=*

s fe E m 3 E s = N == 0 W **

@ @ e 6.4 C g E e e 3 E .a a e C e e e 3e et 5 e W L1 O' ,

S 3r K m* e* C N e a e' a 3m o N e. OF M e b = =

e= I e..

6 O C es 4 =* ==

4 .e ., == ee O =* e u == 2 P e C 13 - C m CQ ec

== " 3

e. == e C ** e ** e **

8 C E =* == ==

O O S O =

CC OO >

O C X 3 C O n.d 6 = m = Z =m ua .4 e e a ee a

=4 C ** e ** E .M E

/ o =* ** C ==

e C e C> eZ 4

i C E e C 6.

OZ e 3 O O 3 0 e eE e a w u J3 w. W Q WN wN E 3 e se w

a. a. e e . e O.

e * *

4. M O O 4 i O M b i N M 4 i

e w

• M

.C. e- N .m

- - - - ~ . , . - . - - .-,, ~ ,- , .,

= _ . . . - - - - - -

4 AININISTRATIVE CCNTROL9 i

6.3 FACILITY STPEF CUALIFICATICNS 6.3.1 Each marter of the facility and Radiation Protection staff l

shall meet or exceed the minimtm qualifications of ANSI N18.1-1971 for conparable positions, except for the Radiological Operations 03ordinator who shall meet or exceed the qualifications of Regulatory Guide 1.8, September t 1975, and the Shift '14chnical Advisor who shall have a bachelor's degree or l

equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for transients and accidents.

6.4 TRAINING 6.4.1 A retrainim and replacement training program for the facility l staff shall be maintained under the direction of the Director Nuclear Division Training and shall meet or exceed the requirements and l

rew.. ..dations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR l

i Part 55.

j

, 6.4.2 A 'Itainim Program for the Emercency Squad shall be maintained under the direction of the Director Nuclear Division Trainity and shall meet ,

l r or exceed the reauirements of Section 27'of the NEPA 03de-1976.

l i j 6.5 REVIEN AND AUDIT 6.5.1 Onsite Safety Comunittee (OSC)

FUNCTICN:

h 6.5.1.1 1he OSC shall fi.:nction to advise the Station Superintendent on all matters related to nuclear safety.

COMPOSITICN:

1 6.5,1.2 'Ihe OSC shall be conposed of the:

Chairman: Oief Ehgineer i Manter: Senior Licensed Operator i l

Manber: Radiation control Ebreman l Member:

Maintenance Engineer Member: Senior Engineer - Station Engineering Monber:

Senior Testing or Study Projects Coordinator Member: Shift Technical Advisor Menber: Gemist rember: Quality (bntrol Engineer l l

l l

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L.-  ;

PFAVER VALIEY UNIT 2 i

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