PLA-3705, Forwards Rev 7 to IST-T-100.0, SSES Unit 1 Inservice Insp Program Plan for Pump & Valve Operational Testing & Rev 4 to IST-T-200.0, SSES Unit 2 Inservice Insp Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04
| ML18026A591 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/31/1991 |
| From: | Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| To: | Chris Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17157B009 | List: |
| References | |
| GL-89-04, GL-89-4, PLA-3705, NUDOCS 9201140161 | |
| Download: ML18026A591 (9) | |
Text
,ACCELERATED DILUTION DEMONSTTION SYSTEM
~i' REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)
ACCESS'XON NBR:9201140161 DOC.DATE: 91/12/31 NOTARIZED: NO FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva AUTH.NAME AUTHOR AFFILIATION KEISER,H.W.
Pennsylvania Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION MILLER,C.L.
Project Directorate I-2 DOCKET 05000387 05000388
SUBJECT:
Forwards Rev 7 to IST-T-100.0, "SSES Unit. 1 Inservice Insp Program Plan for Pump
& Valve Operational Testing"
& Rev 4
to IST-T-200.0, "SSES Unit 2 Inservice Insp Program Plan for D
Pump
& Valve Operational Testing," per Generic Ltr 89-04.
S DISTRIBUTION CODE:
A047D COPIES RECEIVED'LTR i
ENCL Q SIZE'3~
TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code
/
NOTES:LPDR 1
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LPDR 1 cy Transcripts.
05000387 A 05000388 D
RECIPIENT XD CODE/NAME PD1-2 LA RALEXGH,J.
INTERNAL: ACRS NRR/DET/EMEB 7E OC G F E
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1 D
D NOTE TO ALL"RIDS" RECIPIENTS:
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Pennsylvania Power 8 Light Company Two North Ninth Street ~Allentown, PA 18101-1179 ~ 215/774-5151 Harold W. Keiser Senior Vice President-Nuclear 215/7744194 DEC 3 i 199$
Director of Nuclear Reactor'Regulation Attention: Mr. C. L. Miller, Project Director Project Directorate I-2 Division of Reactor Projects U.S. Nuclear regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION REVISION 7 TO UNIT 1 AND REVISION 4 TO UNIT 2 INSERVICE INSPECTION PUMP AND VALVETESTING PROGRAM PLA-3705 FILE R41-2 Docket Nos. 50-387 and 50-388
Dear Mr. Miller:
Attached is Pennsylvania Power &Light Company's Revision 7 to the Unit 1 Susquehanna SES Inservice Inspection Pump and Valve Testing Program and Revision 4 to the Unit 2 Susquehanna SES Inservice Inspection Pump and Valve Testing Program.
These program revisions are a result of compliance with Generic Letter 89-04 and other necessary changes which conform to the guidance ofGeneric Letter 89-04 and therefore, are approved for use in accordance with Generic Letter 8944.
The justification of each change is included in Attachment 1 for Unit 1 and Attachment 2 for Unit 2.
The submittal of these revisions complete PP&L's commitment made with respect to Generic Letter 89-04.
Ifyou have any questions, please contact Mr. C. T. Coddington at (215) 774-7915.
Very truly yours, H. W. Keiser Attachment CC:
NRC Document Control Desk (original)
NRC Region I Mr. G.
S.
Barber, NRC Sr. Resident Inspector Mr. J.
J.
Raleigh, NRC Project Manager irozieo<6i Sti23i PDR ADOCK 05000387 P
Pennsylvania Power & Light Company Two North Ninth Street~Allentown, PA 18101-1179 ~ 215l774-5151 Harold W. Keiser Senior Vice President-Nuclear 215/7744194 May 22, 1992 Mr. James H. Joyner, Chief Facilities Radiological Safety and Safeguards Branch Division of Radiation Safety and Safeguards U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 FILE R41-2 SUSQUEHANNA STEAM ELECTRIC STATION REPLY TO NOTICE OF VIOLATION (387/92-12-01)
PLA-2 Docket Nos. 50-387 50-388
Dear Mr. Joyner:
This letter provides Pennsylvania Power & Light Company's response to the Notice of Violation for NRC Combined Inspection Report 50-387/92-12 and 50-388/92-12 dated April 22, 1992.
The notice required submittal of a written reply within thirty (30) days of the date of the letter.
We trust that the commission willfind the attached response acceptable.
Very truly yours,
. W.
eieer cc:
NRC Document Control Desk (original)
Mr. G.
S. Barber, NRC Sr. Resident Inspector Mr, J, J.
Raleigh, NRC Project Manager FILER41-2 PLA-3772 Mr. J. H.- Joyner bcc:
J.
T.
Kauffman W. F.
Hecht R.
G. Byram H.
G.
Stanley G.
T.
Jones C.
T.
Coddington H.
J.
Marsh W. E.
Licht D.
F.
McGann J.
R.
Miltenberger R.
M. Peal A.
R.
Sabol R.
R.
Wehry H.
D. Woodeshick NRA Corresp. File NR Files TW-16 TW-16 A6-1 SSES A6-2 A24 TW-4 A6-1 SSES A6-1 SSES A2-5 SSES SSES Spec. Off.
A2-4 A6-2 RDK:tah PLA53772,RDK
ATI'ACFBAENT'IO PIA-3772 FILE R41-2 PAGE 1 OF 4 EPLYT AN Tl E FVI TI N
~Vggijgg, (387/92-12-01)
Title 10 Code of Federal Regulations (CFR) 19.12 states, in part, "All individuals working in or f'requenting any portion of a restricted area shall be kept informed of the storage, transfer, or use of radioactive materials or of radiation, in such portions of the restricted area; shall be instructed in...
~
precautions or procedures to minimize exposure Contrary to the
- above, on March 25,
- 1992, the inspector questioned approximately 20 workers inside the Susquehanna Unit 1 drywell (a radiation area) ifthey were aware of the radiation levels in their work area.
None of the twenty were.
Further, through inspector observations in the drywell between March 23 - 25, 1992, workers in the drywell were not making use of the lower drywell radiation levels toward the outside of the drywell shell or of lowe'r radiation level areas within the drywell as waiting areas when not actively required at particular work locations.
The workers were not demonstrating knowledge of the radiological conditions.
Failure to properly keep workers informed of radiation in their work areas constitutes a Severity IVviolation.
1.
Re o
r h V lation The availability of radiological information in the Unit 1 drywell to the worker was inadequate.
Specifically, Health Physics (HP) briefing did not consistently utilize HP survey maps; sources of radiation and low dose rate areas were not emphasized to workers via survey maps and/or postings; and radiological information/postings within the work area did not provide adequate information to the workers for the purpose of ALARA.
h Have T
R A
Pre-job HP briefings to work groups have been expanded and require that the work groups identify the exact work location, the nature ofjob, the work area dose rates, and the estimate of time necessary to perform the job. The Health Physics technician utilizes the most current survey when briefing the work groups, emphasizing general area dose rates,
ATI'ACHMENTTO PLA-3772 FILE R41-2 PAGE 2 OF 4 nearby sources of radiation and low dose rate areas.
Oral acknowledgement concerning the above information is then required of the work group prior to entry to the drywell.
For jobs of a routine nature or jobs requiring numerous entries to the same location the worker must demonstrate his knowledge of work area dose rates prior to each entry.
HP "mobiles" (hanging postings) have been placed on all elevations of the drywell. These "mobiles" provide a worker with a general range of dose rates in his work area.
Placement of the "mobiles" is intended to enable the worker to always see at least one "mobile" while,in the drywell, and therefore reinforce the workers awareness of the presence of radiological hazards.
Informational postings were added at the barricade to high rad areas inside the drywell. This was accomplished by using posting inserts that read, for example: "20 to 30 mr/hr at barricade" N
Enlarged colored maps of the drywell showing sources of radiation (pink), low dose rate waiting areas (green) and general area dose rates for each elevation were placed at the 749'ress out area, the 719'ontrol point and on each elevation inside the drywell, The Manager-Plant Services conducted a tailboard meeting with E&S Construction and Plant Services supervisors to communicate plant management's expectations ofthe supervisor's role in radiological safety, ALARA,and individual accountability.
The Manager-Plant Services conducted a tailboard meeting of HP personnel to reinforce plant management's expectations of Health Physics personnel's responsibility to effectively communicate radiological information to individual workers to enable the work to be accomplished ALARA.
On -April 13, 1992, a "Radiological Safety Note" was issued to Nuclear Department and E&S Construction Nuclear supervision detailing the stations radiological initiatives taken for the Unit 1 drywell.
Topics covered in the Safety Note included the use and location of color coded maps, radiological "mobiles" inside the drywell, and the importance of a'pre-job Health Physics briefing. Supervisors were requested to hold tailboard meetings with their personnel on these initiatives.
ATI'ACHMKNTTO PLA-3772 FILE R41-2 PAGE 3 OF 4 8.
On April 10,
- 1992, the issue of radiation worker awareness was presented to the station's Health and Safety Steering Committee chaired by the Superintendent of Plant.
This action was taken to increase management awareness of this issue and review actions taken.
9.
On April 22, 1992, surveillance activities were conducted by NQA personnel at various Health Physics control points in the UnitI Reactor and Turbine Buildings.
These activities assessed the radiological awareness of a random sample of approximately 40 personnel from various work groups.
Basic surveillance activities consisted of NQA personnel surveying work groups at the work location as to the information relayed to them in the briefing they received from Health Physics.
Specific areas addressed included; (but were not limited to):
1.
RWP number 2.
Was the individual briefed?
3.
Available low dose areas?
4.
Work area dose rates?
5.
Expected total dose?
6.
Status of current surveys?
7.
Radiological postings?
Results of this surveillance indicated that 38 of 40 personnel were aware of work area dose rates.
The remaining two were not in a radiation
'rea.
10.
Individuals are routinely being asked by HP personnel to acknowledge that they understand the radiological information provided at all control point briefings. In addition, Health Physics personnel have randomly selected individuals working within radiological areas and questioned them to determine radiological awareness and knowledge.
Workers interviewed have been able to demonstrate knowledge of the radiological conditions, sources of radiation, work area dose rates, and lower dose rate areas.
ATI'ACHMENT'IO PLA-3772 FILE R41-2
-PAGE 4 OF 4, A
F OJT Training is being developed to reinforce ALARAwork practices at the first line supervisor and worker level. Training is scheduled to be conducted prior to the Unit 2 5th refueling and inspection outage scheduled to begin 'on September 12, 1992.
2.
A Maintenance Self Assessment'Observation Guide on Radiological Safety has been developed.
This self assessment tool is intended to increase oversight of radiological work practices.
3.
Applicable corrective actions identified in this response, to enhance worker awareness of radiological conditions in the drywell, will be incorporated into appropriate procedures prior to the Unit 2 5th refueling and inspection outage scheduled to begin on September 12, 1992.
4.
Additional training on "performing radiological briefings" has been incorporated into the current HP technician routine training cycle. This cycle is scheduled to be completed by August 1, 1992.
D F I m1'ased on (2) above PP&L is in full compliance.