ML20055E305

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Forwards Amend 98 to License DPR-50 & Ser,Revising Tech Specs to Resolve Problems Identified in Insp Rept 50-312/86-15.Recommends That DOJ Be Provided Copy of Amend & SER
ML20055E305
Person / Time
Site: San Onofre, Rancho Seco  Southern California Edison icon.png
Issue date: 04/20/1988
From: Scarano R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Marsh R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20055C206 List:
References
NUDOCS 9007110275
Download: ML20055E305 (8)


See also: IR 05000312/1986015

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MEMORANDtM FOR:

Robert Marsh, Director

Office of Investigations, RV

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FROMt

Ross A. Scarano Ofrector

Division of. Radiation Safety &' Safeguards

$UBJECT:

RANCHO SECO EFFLUENTS RELEASE AMENDMENTS

1

Attached is Amendment No. 98 and the NRC Staff's safety Evaluation Report

(SER)forRanchoSeco,issuedMarch 17 .1988. The amendment revises the

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technical specifications to resolve pro,blems identified in Inspection

Report 86-15.

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Of special interest is the staff's conclusion in the $ER

that ' deficient technical specifications were responsible, in part, for

the offsite contamination prchlam.' Amendment No. 98 also demonstrates

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the extensiveness of the corrective actions required.

We recommend that you provide to the Department of Justice either a cop of

the Amendment and the $ER, highlighting the quoted language, or prefera ly

a copy of this memorandum with the attachments.

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Ross A. Scarano, Director

Division of Radiation Safety & Safeguards

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Enclosure: Amendment No. 98 with SER

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cc.w/ enclosure

Michael Blume

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JEQUEST COPY;

STAPY;

fEQt ESTCOPY;l

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REQUESTCOPY;.

REQUEST COPY ,

WESJ /NO

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YES)

/NO

YES

/NO

YES

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SENDINGTOPDR;

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GYuhas

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Who Initiated Call

Who Was Contacted

Date

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Eric Yochheim

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ChuckHooker(NRC)

GregYuhas(NRC)

3/31/88

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REASON FOR CALL:

To obt.Jn clarification on NRC impressions on the use of the

LLD equations in Tech. Spec. Table 4.21-1.

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RESOLUTION REACHED: Mr. Yuhas' impression was each RHUT and Retention Basin release

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should be counted to the "apriori" established count time

using the Tech. Spec. LLD equation.

He also suolested that

the Ranch establish a position on any questions

hey have

concerning implementation of #nendment 98 and send the letter

to Charlie Willis with a copy to Region V.

The letter should

state if the HDC concept should be used and what the Ranch should

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do.(or will do) if an isotope is less than HDC but greater than LLD.

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REQUEST HADE:

None

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DATE RESPONSE REQUESTED:

N/A

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cc:

Chief Executive Officer, Nuclear MS 209

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.,. -"adiation Protection MS.244

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'AGH, Nuclear Power Production

MS 254

L manager, kuclear Chemistry

MS 250

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AGH,. Nuclear Tech. & Adm. Serv. MS~206

Hanager, Maintenance

MS 254

'

-Director, Nuclear Tech. Serv.

MS 206A

X

Hanager, Nuclear Operations

MS 255

Director, System Rev. & Test Pr. HS 259

Manager, Nuclear Training

MS 296

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Director, Nuclear Ops. & Maint. MS 257

Hanager, Scheduling / Outage

MS 252

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X Director,- Nuclear Plant Support MS 258

Executive Assistant

MS 209

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Director, Nuclear Quality

MS 271

L IIRG

HS 298

L Manager, Nuclear Licensing

MS 286

L NAC (4)

MS 209

Hanager Nuclear Engineering

MS 200- 6 JL Licensing Files

MS 286

X Hanager, Env. Protection

MS 292A

1. RIC Files

MS 224

Public Information

MS 204

X Mana er, Plant Performance

MS 258-

,

H.P &.c

HS 202

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(X) COPY HANDATORY

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RANCHO SECO NUCLEAR GENERATING STATION

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CHIEF EXECUTIVE OFFICER, NUCLE AR DIRECTIVE

April 1, 1988

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Distribution

CEO-ND 88-02

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Revision 0

OFF-SITE RADICIDGICAL RELEASE CRITERIA

susJrcT

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Define and implement policies for the release of

radioactive materials,.potentially radioactive

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PURPOSE

materials, and nonradioactive materials in. liquids and

solids from the Rancho Seco site.

Applies to all organizations who havs decision-making

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accountabilities in relation to analyzing and/or

SCOPE:

releasing radioactive and potentially radioactive

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This would normally be

materials from the site.

limited to the Radiation Protection, Chemistry,

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Operations, and Environmental Protection Departments,

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10CTR20, 10CFR50, and NRC IE Bulletin No. 80-10,

" Contamination of Nonradioactive. System and Resulting

REFERENCES:

Potential for Unmonitored, Uncontrolled Release of

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Radioactivity to Environment".

..You are hereby directed to develop and implement procedures

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and

using the following criteria when sampling, analyzing,ive

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DIRECTIVE

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releasing liquid and solid materials that are radioact

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The

er.potentially radioactive, from the Rancho Seco site.

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specific sampling frequ'encies and methods are to be addressed

in Chemistry and/oc Radiation Protection procedures as

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appropriatet

1.

Criter3a For Environmental (Annandix I Related)

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Lieuids

The following samples will be counted to meet

Lower Limit of Detection (LLD) levels at a

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LLD ensures

frequency as specified by1 procedure.

compliance with 50% of 10CFR50, Appendix I

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criteria and is listed and defined in Technical

Specifications Table 4.21-1.)

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Plant affluent (upstream of Retention Basin)

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Regenerant Holdup Tanks A or B

Plant storm drains (unmanitored)

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- Folsom South Canal Inlet

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CEO-ND 88-02

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April 1, 1988

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2.

Criteria For Environmental Lieuid Releases:

Retention Basins Nort h r South will be sarpled

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prior to release at an LLD sensitivity stated in

Item 1 above.

3.

criteria For Seecial case Lieuid Accumulations:

When samples are required for standing water,

spills, etc., in areas that are contaminated or

potentially contaminated (e.g., blocked off stora

drains in " tank fara", solidification pad, spills

and/or drainage from water sources inside

" controlled access areas", etc.), they shall be

counted to meet a minimum sensitivity of LLD

levels if they are to be released directly off-

site.

If these liquids are to be pumped to RHUT

(A/B), they do not have to be analyzed prior-to

pumping to RHUT (A/B).

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criteria For onen eyele cooline Water systemmt

These systems are considered nonradioactive and

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shall be sampled to meet a minimum required

W ,/ ,p ,g & M

sensitivity of 3E-07 uCi/ml gross activity in

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de0# '2#

accordance with NRC IE Bulletin 80-10.

The

sampling frequency and sensitivity shall be as

$r -/ gped defined by procedure,

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Nuclear Service Spray Ponds A and B

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Cooling Tower Basin Blowdown

Sewage Treatment Plant Final Effluent

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HOTEt

If any sample ingicates activity greater

than 3E-07 uCi/ag gross activity, the

sample will be reanalyzed by gamma spec

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to LLD levels, and for M-3 to a minimum

sensitivity of 5E-06 uCi/ml.

ci'itairia*For" closed cycle coolina Water Systems:

5.

Theseisysiensare!consideredEnonradioactive.and

<shall*bersampled!to' meet,a minimum sensitivity of-

J5E-06'uCi/ml H-3:in'accordance with NRC IE + -

Bulletin!80-10'- The '
saniplingi frequency;; shall; be;

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~as define.d:byJprocedure.7-

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. CEC-ND 88-02

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April 1, 1988

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Component cooling Water System

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Control Rod Drive Cooling Water

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Nuclear service cooling Water A and'B

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MQ238:

(a): Drainage of,these. systems

shall be'to:RNUT.A or 3:only.-a

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(b)

If any sample indicates M-3

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.activitylgreater;than'5E-06

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-uci/al N-3, the sample:will

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.be reanalysed by- amma,spoo'

-to a minimus sens tivityfof ~

'33-07:uci/al.

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6.

Crntaria For secondary Plant Includine Turbine

'Butidina summat

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A.

Makaue Damineralizar Pit sumn

Is normally pumped to RNUT C and is not

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required to be sampled.

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B.

RMUT C

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Nonradioactive storage tank

sampled. prior-to.

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release to a minimum sensit vity of-3E-07

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uCi/al gross activity.and SE-06 uCi/al H-3,

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l80-10in;accordance with NRC IE Bulletin

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If.RNUT C sample indicates activity

greater than 3E-07 uci/a1 gross

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activity, and/or greater than 5E-06

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uCi/al H-3, the sample will be

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reanalysed by gamma spec to a minimum

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sensitivity, equivalent to LLD levels.

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C.

condannatapitsunnandcondensataholisher

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REER

The Condensate Pit Sump and contensate

Polisher Sump are pumped (indirectly or

directly) to RNUT A or B and are not normally

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sampled.. They may be sampled on an as-needed

basis after an actual or suspected primary-

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to-secondary steam generator tube leak.

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CEO ND 88-02

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April 1, 1988

D..

Condensate Storace Tank (CST _)

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Prior to rejection of hotwell and/or

condensate polisher effluent water to the

CST, the water shall be less than 3E-07

uCi/ml gross activity and 5E-06 uCi/ml H-3.

During rejection, the water should be

periodically sampled to meet this criteria.

E.

Leakina Valves. Packins Leaks. Etc.

Water that leaks from' nonradioactive systems,

as defined by this document, through valve

leaks, packing leaks,1 system maintenance,

etc.,.shall be considered nonradioactive and

no additional sampling is required.

7.

criteria Por Materials To Be sent off-sitet

HQTE:

If the source of-the material!can be

traced to a known nonradioactive

system and/or component, the sample

can be shipped and

without sampling a/or disposed of

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nd counting.

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A.

Lieuid and_ solid'sammies

Samples of liquid'or solids to be sent off-

site for chemical attd/or radiological-

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analyses (e.g., waste diesel fuel oil-and

pump oils, water, dirt, charcoal, resin,

etc.) shall be analyzed to a minimum

sensitivity of 3E-07 uCi/ml (or uCi/g) gross

activity. and 5E-06 uC1 'al (water only) H-3.

samples indicating last than 3E-07 uci/ml (or

uCi/g) gross activity a ut less than SE-06

uCi/ml H-3- (water sampit s) may be treated as-

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nonradioactive materials.

Samples indibating greater than 3E-07 uCi/ml-

(or uCi/g) gross activity and/or greater than

5E-06-uci/ml H-3 (water samples) shallLbe

.handlo3 as follows:

(1)

The samples can only be sent to

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facilities licensed to receive the

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radioactive material.

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cro-ND 88-02

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April 1, 1983

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(2). samples with greater than 2E-03 uci/g

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(uci/a1 as appropriate) activity are-

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subject to Federal Department of

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Transportation regulations while in

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transit.

B.

Llauld Materiala

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Liquids (such as oil or oil-water mixtures)

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to be sent off-site for disposal, shall be

sampled and analysed to a minimum sensitivity.

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of 3E-07 uci

liguid is an/a1 gross: activity.

If the

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oil-water mixture

the water

shall be analysed to e minimum, sensitivity _of

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SE-06 uCi/ml H-3.-

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Liquids' indicating less than 3E-07 uci/ml

groes activity and less than SE-06 uci/al H-3

(water) ma

materials.y be treated as nonradioactive

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Liquids indicating greater than.3E-07 uCi/mi

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gross-activity and/or greater than 5E-06

uCi/ml H-3

radioactive (waste according to plantwater) shall be

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procedures.

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C.

Solid Materials

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The disposal'of solid materials (such as

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dirt, charcoal, resin, etc. ) ~ will be

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addressed <bytthe.Below-Regulatory Concern.

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~(BRC)? program;which is(being developed:by the

EnvironmentalTProtectiontDepartment.- This-

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program 11s-scheduled for completion'in the

fall of 1988.

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8CHEDULas

Effective April 1, 1988.

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CLOSEOUTt

An Action Plan will be developed by April 15, 1988, to

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proceduralize these criteria.

Procedures will be revised

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and this N00 closed out by June 15' 1988.

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7/Cafi Andognini /)

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M ief Exec 6tive Opicer/f g ,

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Nuclear

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Distribution:

B. Croley

J. Firlit

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B. Harris

B. Kemper

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D. Kauter

P. Lavely

J. McColligan

E. Yochheim

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CEO-ND 88-02-

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April 1, 1988

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Nuclear Directors

Roseanne Martinez

Nuclear Depart.nent Managers

Brad Thomas /Xerry Shearer

Board of Directors

Jim O'Hanlon

. Richard X. Byrne

Bob Ferguson

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.....................................................................

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To:

Office of the Chief Executive Officer, Nuclear .

Mail stop No. 209

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ACKNOWLEDGE:

Date Received:

CEC-ND 88-02

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