ML20082H750
| ML20082H750 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/21/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20082H725 | List: |
| References | |
| PROC-910821, NUDOCS 9108260256 | |
| Download: ML20082H750 (10) | |
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-f CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC Pl#TI PROCESS CONTROL PROGRAM (PCP)-
DOCKET NOS,-50 324 AND 50 325 REVISION 3 L
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' 1.0 Scopet This' program establishes the management system and controls that the Brunswick Steam Electric Plant (BSEP) uses to ensure safe and effective solidification and-dewaterin5 of various low level radioactive waste liquids and slurries for off site disposal.
2.0 obiective It is_the objective of this program that the solidification and/or dewatering of various low level radioactive waste liquids and slurries (including oily waste) for off-site disposal will be performed by qualified vendors. The quality of the solidified and/or dewatered product shall meet or exceed regulatory requirements and the disposal site criteria prior to release from the Brunswick site for shallow land disposal.
3.0 Manacement Procram 3.1 Responsibilities 3.1.1 The Manager - E&RC is responsible for:
3.1.1.1 Ensuring the waste is shipped in accordance with the appropriate state and federal reSulations.
3.1.1.2 Advising the General Manager on the appropriate technical standards, regulations, and requirements as related to solidification, dewatering, and shipping.
3.1.1.3 Ensuring the vendor's Process Control Program, operating procedures, and-proposed contractual agreements are reviewed and advising the General Manager as to their. adequacy.
3.1,1.4 Retaining vendor supplied documentation for NRC inspection and review.
3.1.2- The Manager - Operations is responsible for monitorin5 vendor operations to assure compliance with Technical Specification 3/4.11.3, CP&L practices and procedures, as well as contractual agreements.
3.1.3 The Manager - Health Physics Unit of the Nuclear Plant Support Section is responsible for advising the Manager - E&RC'on:
3.1.3.1 The appropriate technical standards, regulations, and requirements as related to solidification, dewatering, and shipping.
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- 3,1.3.2 The adequacy of the vendor's Process Control Program, l operating procedures, and proposed contractual agreements.
32 Specification for Vendors The qualified-solidification vendor will: )
- 3. 2.1- Provido a qualified process control program or a program I approved by:
3.2.1.1 NRC 3.2.1.2 Disposal site licensee d2IE -
Qualified process control program has been interpreted to mean !
that testing of the product is underway (to m et the 10CFR l Part 61 requirement) or test _results have boca transmitted to j the Nuclear Regulatory Commission in the form of a topical report.-
'3.2.2- Demonstrate the ability to meet:
3.2.2,1 NRC solidification standards 3.2.2.2 Disposal site specifications for solidified liquid wastes 3.2.2.3 NRC' dewatering standards 3.2.2,4 Disposal site specification for freestanding liquids 3.2.2.5 DOT shipping regulations 3,2,2.6 CP&L radiation protection procedures and practices-3.2,3 Provide-documentation on the following for CP&L review, evaluation, and retention:
3.2.3.1. . Solidification and dewatering system design including a sketch of the processing system (s) 3.2.3.2- -Identification of solidification agent (s) 3.2.3.3 Operating process control procedures with the process control parameters identified.(including those for-
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exothermic reactions _ required to;be met prior to container's closure) and provisions to verify the-absence of free liquids PCP (BSEP)- 2 Rev. 3 PCP.MSC
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3.2.3.4 Results of process tests including: l t
A. Identification of the representative sanple of every [
tenth batch j B. Identification of actions taken if sample fails to f verify solidification C. Formulation used by the process 3.2.3.5 Topical or qualified report for dewatering j t
3.2.3.6 Topical or qualified report for high inteCrity l containers 3.3 'Prograin Operations k 3.3.1 The vendor will solidify or devater and package the supplied liquid waste slurries (including the oily waste) according to their hocess Control Program.
3.3.7 The vendor will perforin the tests described in their Process control Program.
3.3.3 The vendor will supply the Manager -E6RC and/or the Manager + Operations with all doctwentation required to demonstrate compliance with solidification and/or dewatering requirements.
3.3.4 The vendor will report actual or suspected dev.stions from this procedure, the vendor's QA plan, the vetulor's procedure or other abnormalities to the Manager -
Operations ENP imrediately. These deviations inay be initially provided verbally; however, a written report will be nrovided within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> which discusses the-how, when, vnere, why, how much, and appropriate corrective
-actions.
3.3.5 The Manager-- E&RC will retain vendor supplied documentation required to demonstrate compliance with
-solidification and/or dewatering requirements and standards. (This does not include documentation-of-Technical Specification Surveillance Requirement 4 11.3, which is the responsibility of .the flanager - Opers cions.) .
4.0 linnagement/ contractor InternettDnt .
4.1 The vendor is accountable to the Manager Operations for the polidification and/or dowatering of liquid wastes.
4.2 _The E&RC subunit handles the shipping of solidified and dewatered wastes and maintains. required shipping documentation.- The vendor and the E&RC Shipping Foreman inay communicate on these mctters as necessary.
_ POP.MSC~
V
ATTACitMENT 1 -
REOUEST TOH OFF SITE Dose CALCULATION MANUAL CHANGE
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2nd Party Nucitar Safety Keviewer -
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, .' ATTACllMENT 2 (Cont'd)
REVIS!ON 2 10CFR50.59 PROGRAM MANUAL PageoO A*ITAOIMENT A Q%L SAFETY REVIEW PACKAGE Page 1 of
- i PART I: SAFETY ANALYSIS (See instructions in Section 8.4.1)
(Attach additional sheets as necessary)
DOCUMENT NO. tir u tr~ iv_<r e en <ut <! r en4n REV. NO. II DESCRll' TION OF OlANGE: W !! Urrl 5 && ch Iln j [nv t/In . fer;ry begru,; ,
O Perlaml elk u n ,' r %lve uox 4 a' o rklal wem . A) EsN e e ?II '
sI w %..<,l n,in< J.er nv <ter. - u!,a a i l/ti ! . /,, ,<.a<<.af i
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REFERENCES:
on c. m .
) 0 kla,en l fm; hcdun s - %rhe.1, L /2. l . To Me ;,12,I-l Cc 1:e , a . > .1. I O AI 109 Rev. 001 Page 76 of 87 l L -. - . .
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. . ATTACllMENT 2 (Cont'd)
REVISION 2 10CFR50.59 PROGRAh! hiANUAL Page e3 ATTACllhiENT A C
CP&L SAFETY REVIEW PACKAGE Page of
- PART IYr UNREYlEWED SAFETY QUESTION DETERh11 NATION DOCUhtENT NO. c.1F n tr on r < wat nr a Am utsi_ REV.NO. ll Using the SATETY ANALYSIS developed for the change, test or expenment, as well as oth, r requurd references (LICENSING BASIS DOCUbiENTATION Design Drawings, Design Basis Documents, codes, etc.), the preputr of the Urutviewed Safety Quesnon Determmanon must directly answer each of the following seven quescons and make a detenntnauon of whether an UNREVIEWED SAFETY QUES' DON exists.
A WRITTEN !! ASIS IS REQUIRED FOR EACll ANSWER
.Yu So
- . hiay the proposed acnvity increase the probability of occurrence of () {}-
an accident evaluated previously in the S AFETY ANALYSIS REPORT 7
<,w Af%ehl
- 2. Niay the atuposed activity increase the consequences of an accident [] [}'
reviousl the SAFETY ANALYSIS REPORT?
evaluatec Oc t p!Harc /y
- 3. Stay the proposed activity increase the probability of occurrence of (1 [}'
a malfuncuan of equipment important to safety evaluated previously in the SAFETY A A YSIS REPORT 7 he Affar e
.t . hiay'the proposed acuvity increase the consequence of a () [}'
malfuncnon of equipment imxnant to safety evaluated previously in the SAFETY AN SIS E. PORT 7 De ML*
- 5. hiay the proposed activity create the possibility of an accident of a () V than any evaluated previously in the S AFETY different
^"TS' n typ*M l
O'AI 109 Rev. 001 Page 79 of 87 l
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'i TACllMuff 2 (Cont'd)
REVISION 2 10CTR$0.59 PROGRAM MANUAL Page 64 A'ITACIIMENT A CP&L SAFETY REVIEW PACKAGE Page t of A PART IV: (Continued)
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- 6. May the proposed activity create the possibility of a malfunction of [] (}/
equipment important to safety of a different type than any evaluated previously in the SAFSTY ANALYSIS REPORT 7 5e /) f t u r l .>./
7i Does the proposed activity reduce the margin of safety as defined in 0 [V the basis of any T;chnical Specukation?
G, 4 W rA./
S. Based on the answers to questions 1 7. does this item result in an [] l}'
UNREVIEWED SAFETY QUESTION 7 If the answer to any of the questions 17 is "Yes", then the item is considered to constitute an UNREVIEWED SAFETY QUESTION.
- 9. Is PNSC review required for any of the following reasons? [] [V If. in answering question 1 or 3 "No," It was determined that the pinbability increase was small relative to the uncertainties: or, in answering question 2 or 4 "No," it was determined that the doses increased, but the dose was still less than the NRC ACCEPTANCE LIMIT:
or,in answering question 7 "No." a parameter would be closer to the NRC ACCEPTANCE LIMIT. but the end result was still within the NRC ACCEPTANCE LIMIT; then PNSC reviewis required.
REFERENCES:
PS M - h day T.:ble e f fe,ha t s ga i w t). c Tor tr..u I hw/iea f *n s. IJ I s4. IJ. I ia bl4 3 IJ l - l 7 i $'. 't la // . L-t DC m ~
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This Urutviewed Safety Question Determination is for the following DISCIPLINE (s):
- (Addidonal Part IV forms may be included as appropriate.)
0 Nuclear Plant Operations O structural
[] Nuclear Engineering 0 Metallurgy-0 Mechanical WChemistry/ Radiochemistry
[] Electncal [] Health Physics-
- () Instrumentation & Control . O Administrative Controls O AI 109 Rev. 001- Page 80 of 87 j
l Pago 8 of 8 I UNREVIEWED SAFETY QUESTION DETERMIllATION i OFF-SITE DOSE CALCULATION MANUAL REVISION 11
- 1. TilI'3 REVISION TO TIIE ODCM DOES NOT EFFECT ANY INITIATING SYSTEMS, STRUCTURES, OR COMPONENTS. Tile Cl!ANGES MADE TO Tile ODCM WERE (1) ADD 5 ADDITIONAL TLD's TO Tile ENVIRONMENTAL MONITORING PROGRAM IN TABLE 4.0~1, (2) REPLACE Ti!E OLD MAPS IN SECTION 4.0 WITil NEW MAPS, AND (3) REMOVE T!!E OLD INSTRUMENT NUMBER FOR Tile MAIN STACK SYSTE!4 EFFLUENT FLOW RATE MEASUREMENT DEVICE ON PAGE E-2 OF APPENDIX E. IMPLEMENTATION OF TilIS REVISION WILL NOT INCREASE Tile PROBABILITY OF ANY ACCIDENT PREVIOUSLY EVALUATED IN TIIE SAFETY ANALYSIS REPORT.
- 2. Ti!ESE CllANGES TO Tl!E ODCM DO NOT ALTER OR Cl!ANGE Ti!E INITIAL CONDITIONS OF ANY ACCIDENT OR EFFECT MITIGATING SYSTEMS, STRUCTURES, OR COMPONENTS. Ti!EREFORE , Tile Cl!ANGES WILL NOT INCREASE Tile CONSEQUENCES OF ANY ACCIDENT PREVIOUSLY EVALUATED IN Tile SAFETY ANALYSIS REPORT.
- 3. TIIESE CilANGES TO Tile ODCM EN!!ANCE Tile ENVIRONMENTAL TLD MONITORING PROGRAM AND DOEs NOT EFFECT Tile PERFORMANCE OR OPERATION OF ANY IMPORTANT TO SAFETY EQUIPMENT AND WILL NOT INCREASE T!!E PROBABILITY OF OCCURRENCE OF MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY PREVIOUSLY EVALUATED IN Ti!E SAFETY ANALYSIS REPORT.
- 4. IMPORTANT TO SAFETY EQUIPMENT IS NOT EFFECTED BY Tl!IS PROCEDURE AND TilEREFORE THE CONSEQUENCE OF A MALFUNCTION OF IMPORTANT TO SAFETY EQUIPMENT WILL NOT BB INCREASED.
- 5. IMPLEMENTATION OF THIS Cl!ANGE WILL NOT CREATE Tile POSSIBILITY OF AN ACCIDENT OF A DIFFERENT TYPE TilAN PREVIOUSLY EVALUATED I N ' Til E SAFETY ANALYSIS REPORT. Cl!ANGES TO Ti!E MONITOR DESIGNATION IS ADMINISTRATIVE IN NATURE AND Tl!E ADDITION OF Tile FIVE ADDITIONAL TLD's TO SECTION 4.0 OF TIIE ENVIRONMENTAL MONITORING PROGRAM ENHANCES Ti!E PROGRAM.
- 6. THE CllANGES DO NOT EFFECT ANY EQUIPMENT IMPORTANT TO SAFETY AND TilEREFORE WILL NOT CREATE Tile POSSIBILITY OF A MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY OF A DIFFERENT TYPE TilAN PREVIOUSLY EVALUATED IN Tile SAFETY ANALYSIS REPORT.
THE ADDITION OF Tile FIVE ADDITIONAL TLD's AND UPDATING THE MAPS IN SECTION 4.0 OF Tile ODCM ENHANCE Tile PROGRAM AND AID IN ENSURING COMPLIANCE TO REGULATORY REQUIREMENTS.