ML20212M532
| ML20212M532 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 02/18/1987 |
| From: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Shetterly H AFFILIATION NOT ASSIGNED |
| Shared Package | |
| ML20212M502 | List: |
| References | |
| NUDOCS 8703120062 | |
| Download: ML20212M532 (1) | |
See also: IR 05000293/1982020
Text
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CUCLEAR RE!ULATORY COMMIS$10N
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Kim s er rcussia. esumsvi.vania toers
FEB 161967
Howard.E. Shetterly
P.O. Box 795
-Manomet, Massachusetts 02345
Dear Mr. Shetterly:
Subject: NRC Inspection Report 50-293/82-20
It has been brought to my attention that you were' unable to locate a Nuclear
Regulatory Commission Inspection Report at the Local Public Document Room at
the Plymouth Public Library.
The document you seek is Inspection Report 50-293/82-20, and it is available
from the NRC Public Document Room, under accession number 8208300245. I have
enclosed a copy of the report.
I regret any inconvenience you may have experienced in obtaining this report.
If you should experience difficulty in obtaining any NRC document relating to
Pilgrim Nuclear Power Station please do not hesitate to contact James T. Wiggins
of my staff at (215) 337-5128.
Sincerely,
W 111am . Kane, Director
Division of Reactor Projects
Enclosure: As Stated
0703120062 870304
,
ADOCK 05000293
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ENCLOSURE-
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AUG 131982
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Docket No.-50-293
Boston Edison Company M/C Nuclear
ATTN: Mr. William D. Harrington
Senior Vice President, Nuclear
800 Boylston Street.
- Soston, MA 02199
-Gentlemen:
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Subject:
Inspection No. 50-293/82-20
This refers to the special safety inspection conducted by Mr. R..L.-Nimitz of
this office on June 11-13, 1982 at the Pilgrim Nuclear Power Station, Plymouth,
Massachusetts of activities authorized by NRC License No. DPR-35 and to the
- discussions of our findings held by Mr. Nimitz with Mr. R. D. Machon and other
members of your staff at the conclusion of the inspection, and to a subsequent
telephone discussion between Mr. R. W. Starostecki, Director, Division of Project
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and Resident Programs, of this office and you on June 15, 1982.
Areas examined during this inspection are described in the NRC Region I Inspection
Report which is enclosed with this letter. Within these areas, the inspection
consisted of selective examinations'of procedures and representative records,
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interviews with personnel, measurements made by the inspector, and observations
by the inspector.
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. ithin the scope o'f this inspection, no violations were observed.
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In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures
will be placed in the NRC Public Document Room unless you notify this office, by
telephone, within ten days of the date of this letter and submit written applica-
tion to withhold information contained therein within thirty days of the date of
this letter.
Such application must be consistent with the requirements of
2.790(b)(1). The telephone notification of your intent to request withholding,
or any request for an extension of the 10 day period which ycu believe necessary,
should be made to the Supervisor, Files, Mail and Records, USNRC Region I, at
(215)-337-5223.
No reply to this letter is required.
Your cooperation with us in this matter is
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appreciated.
Sincerely,
Original Signed By:
Thomas T. Martin,
irector
Division of Engineering and Technical
Programs
h
Enclosure: NRC Region I Inspection Report Number 50-293/82-20
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, Boston Edis:n company
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A. V. Morist, Manager, Nuclear Operations Support
R. D. Machon, Nuclear Dperations Manager - Pilgrim Station
Joanne shotwell, Assistant Attorney General
Jon N. Sonsall, Chairman, Department of Public Utilities
Plymouth Board of Selectmen
Plymouth Civil Defense Director
Senator Eduerd P. Kirtry
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
Commonwealth of Massachusetts (2)
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-Report No. 50-293/82-20-
Docket No.
50-293
Category
C
License No. DPR-35
Priority
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Licensee:
Doston Edison Company
80_0 Boylston Street
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Boston. Massachusetts 02199
Facility Name:- P11 aria Nuclear Power Station
Inspection At:
Plymouth. Massachusetts
Inspection Conducted: June 11-13.1982
Inspectors:
R.L N
Blsl B 2
R. L. Nimitz, Radiat'fon Specialist
date
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M4rs&&
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M. H. Mt:Brlde, Ph.D., Radiation Specialist
date
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b
Al 5 } St
J. J. Kottan, Radiatun Laboratory
date
Specialist
. Approved by:
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E. G. Greenman, Acting Chief, Facilities
date
Radiation Protection Section
Inspection Summary:
Inspection on June 11-13. 1982 (Inspection Report No. 50-293/82-20)
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Areas Inspected:
Special, announced inspection of initial licensee actions after
spent resin was found on roof-tops and pavement within the protected area of the
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Pilgrim Station on June 11, 1982. Areas inspected included:
initial contam-
ination identification, contamination surveys, posting and barricading, resin
removal, resin source determination, notifications and initial and long term
planned corrective actions. Upon arrival at the site at 10:30 p.m. on June 11,
1982, the inspectors toured the site to review the extent and control of the resin
contamination. The inspection involved 33 inspector-hours onsite by three
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region-based inspectors.
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Results: No violations were identified.
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DETAILS
1.
Persons Contacted
W. Armstrong, Deputy Manager, Nuclear Dperations
W. Anderson, Watch Engineer
J. Bunning, HVAC Supervisor, Johnson Controls
L. Dooley, Health Physics Engineer
8. Elderidge, Senior Radiological Engineer
J. Frazer, Instrumentation and Control Supervisor
- R. Machon, Nuclear Operations Manager
- C. Mathis, Deputy - Nuclear Dperations Manager
A. Richards, Health Physics Engineer
K. Roberts, Chief Maintenance Engineer
J. Smallwood, Chemical Engineer
- P. Smith, Chief Technical Engineer
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V. Stag 11ola, Senior Waste Management Engineer
- denotes those persons attending the exit interview on June 13, 1982
The inspector also contacted other licensee personnel during the inspection.
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2.
Purpose
The purpose of this special inspection was to review the licensee's
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actions after spent resin was found on roof-tops and pavement within the
Protected Area of the Pilgrim Station on June 11, 1982.
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3.
Description of Identification
During a tour of the Retube Building Roof (see Figure 1) at about 1:00
p.m. on June 11, 1982, a Radiation Protection Technician saw resin in the
building's rain gutters.
Subsequent contamination surveys of small piles
of the resin (about several grams) indicated activity levels of 100-200,000
disintegrations per minute (DPM).
4.
Inspector Review
The inspectors reviewed the following licensee actions taken after ident.1-
fication of the spent resin.
4.1 Contamination Surveys
The review of this area indicated that, when the resin was found the
licensee immediately performed surveys of the entire Protected Area
and selected areas of the Licensee Controlled Area. The surveys
were completed within about 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of initial identification of the
resin.
Areas surveyed included: roof-tops of other buildings, pavement
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areas, storm drains, security access area, parking lots, automobiles
and the shore front area.
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The licensee identified resin contamination on the Reactor, Turbine,
Administration, and Augmented Off-Gas Butidings.
Resin was also
identified on two areas of pavement (see Figure 1).
No resin contamination was found off site or in the store drains.
Based on this review, the licensee performed adequate initial contamina-
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tion surveys to define the extent of resin contamination.
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No violations were identified.
4.2 Personnel Contamination Surveys
The licensee's normal personnel contamination survey requirements
includes the requirement that personnel exiting the Controlled Area
perform a complete whole body frisk.
In addition, personnel are
required to pass through high sensitivity portal monitors at the
security access / egress area.
Subsequent to the resin identification, the licensee initiated a
requirement that all personnel exiting the security access / egress area
perform contamination surveys of their shoes with a thin window detector.
The requirement to perform the additional surveys was implemented
within about two hours after the initial identification.
No shoe contamination was identified.
No violations were identified.
4.3 Posting and Barricading
The review of the posting and barricading of selected contaminated
areas, indicated the licensee had posted and barricaded the areas in
an expeditious manner and in accordance with station procedures.
No violations were identified.
4.4 Spent Resin Removal
The review of this area indicated the licensee initiated vacuuming of
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the resin from the contaminated areas and from the Reactor Building
Contaminated Ventilation Exhaust System in an expeditious manner.
To further expedite the clean-up operation, the licensee ordered
additional vacuum cleaners. These vacuum cleaners were to be flown in
by airplane.
During removal of resins from the pavement and roof-top areas, the
licensee also collected airborne radioactivity samples. No airborne
radioactivity was identified.
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4.5 Source Identification / Initial Corrective Action
The inspectors' review of licensee actions taken following .identi-
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ficatioa of the spent resin indicated that the licensee:immediately
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initiated an investigation to determine the source of the resin contami-
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The licensee's initial findings indicated the resin was entering the
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ventilation system during resin cleaning operations. The licensee
subsequently suspended all operations which could result in further
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resin releases to ventilation system duct work.
Figure 2 provides the
apparent resin contamination / release pathway.
The inspector's discussions with licansee representatives regarding
the initial identification of spent resin in the ventilation system
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showed that spent resin had been identified in the ventilation system
prior to the identification of the resin on roof-tops. The inspector
also noted that dry radioactive resin was found in the "B" Stand By
Gas Treatment (S8GT) System on September 27, 1981.
(Inspection
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Report 50-293/82-01).
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The $8GT System exhausts air from contaminated ventilation systems in
the Reactor Building as does the Reactor Building Contaminated / Area
Exhaust System.
Consequently, the inspector noted the identification
of spent resin in the SBGT System would serve as an indication of
possible resin contamination of the Reactor Building Contaminated Area
Exhaust System. The latter system vents to atmosphere via the Reactor
Building Vent Stack.
Licensee representatives stated that in September 1981, the Reactor
Building Contaminated Area Exhaust Filters were found to be by-
passing, apparently due to improper filter fit and degradation and
were subsequently replaced.
The licensee representatives stated that
the contamination most likely exited the plant vent via the by pass
prior to the repair of the filters.
The inspector indicated that circumstances surrounding the initial
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ventilation system contamination and the licensee's actions taken
would be reviewed further during a subsequent inspection.
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(50-293/82-20-01)
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4.6 Notifications
The inspectors reviewed the identification of the spent resin event
with respect to the requirements of 10 CFR 50.72, " Notification of
significant events." Upon evaluation it was determined that the
detection of the contamination did not constitute a significant event
as described in 10 CFR 50.72.
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Inspector discussions with the Pilgrim Station Senior Resident Inspector
indicated that he noted additional personnel activity (about one hour
after the licensee's initial discovery). and questioned licensee representatives
regarding this activity.
Licensae representatives stated that the additional
activity was the result of resin identification on roof-tops.
The Senior Resident Inspector subsequently notified NRC Region I. The
licensee also notified the NRC Operations Center of the resin contamination.
No' violations were identified.
5.
Long Term Corrective Action
The inspector met with licensee representatives on June 13, 1982 to
discuss the licensee's plans for long term corrective actions.
As a result of these discussions and a followup telephone conversation on
June 15, 1982 between the Director, Division of Project and Resident
Programs, NRC Region I and the licensee, a Confirmatory Action Letter
(No. CAL 82-19) dated June 16, 1982, was sent to the licensee to document
the NRC's uMerstanding of planned actions.
The letter stated the NRC understanding that the licensee would undertake
ynd complete the following actions:
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Discontinue back flushing, regenerating or ultrasonically cleaning
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condensate demineralizer spent resins until the source of the resin
contamination of ventilation systsas is identified and corrective
actions taken for its cause.
In the event long term plant design
changes are needed to correct the cause of the resin release to the
. ventilation system, resin cleaning operations may be perfomed
provided that:
a) appropriate procedure revisions and other admini-
strative controls are established to prevent further resin releases
to the ventilation system; b) a test of the adequacy of the procedure
revisions and other administrative controls is perfomed using clean
resin and; c) the integrity of the Contaminated Exhaust Ventilation
filters has been verified by DOP testing.,
Inspect or test all potentially effected sefety-related ventilation
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system components (e.g. Secondary Containment Isolation Dampers) to
verify their operability and the absence of resin.
In the event
resin cortamination is identified, the resin will be removed. The
results of this inspection shall be documented for subsequent NRC
review.
Inspect' clean air intake ventilation filters or ducts for all potentially
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effected station structures to verify absence of resin.
In the
event resin contamination is identified, the resin will be removed.
The results of this inspection shall be documented for subsequent
NRC review.
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Inspect the Reactor Building plant vent monitor to verify its opera-
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bility and the absence of resin in the sampling system. The results
of this inspection shall be documentsd for subsequent NRC review.
Establish a surveillance and preventative maintenance program for
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contaminated ventilation exhaust systems to ensure exhaust filter
integrity. This program will also include provisions for system
inspection to identify resin accumulation.
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Provide to the NRC Region I office by July 15, 1982 a report. detailing
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the history and extent of the duct contamination, its causes, and
the circumstancan surrounding the release of radioactive material.
This report will also describe th corrective actions taken and the
additional management oversight initiated to prevent recurrence.
The licensee provided the requested report in a letter dated July 15,
1982. The licensee's implementation of the remaining NRC understanding
will be reviewed during a subsequent inspection (50-293/82-20-02).
6.
Exit Interview
The inspector met with licensee representatives (denoted in Section 1 of
this report) on June 13, 1982. The inspector summarized the scope and
findings of the inspection.
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PILGRIM STATlON SITE PLAN
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SPDff RESIN CONTARINATION
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JUNE 11. 1982
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Indicates extent
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cf contamination
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j l . Administration Building Roof - pockets 100K - 200K dpa
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Pavement - along' curb. 20K - 80K dpa
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2.
Reactor Building Roof - clean
8.
Pavement
along curb.100K - 200K dpm
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3. . Turbine Building Roof - pockets.100K dpa
9.
Plant Vent - Point of Release
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A0G Building - pockets. 200K dpa
5.
Retube Building - pockets. 2000( dpa
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Main Tran<fnemer Area - IK - 25K dem (small areas)
- Assumed 105 Detector Rfficiency
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FIGURE 2
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SPENT RESIN CONTANINATION/ RELEASE
PATildAY
Reactor Building Yent
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To Main Stack
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Reactor Building
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Contaminated Area
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Exhaust Filters and Fans
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Standby Gas
Treatment System
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Scrubber
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Six Condensate
Vent from
Vent from
namineralizar
Cation Regeneration
Resin Storage
Vent Valves
Tank
Tank
1.
Possible source prior to repair.
2.
Apparent source during backwarhing.
3.
Possible source during resin transfer
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4.
Filters found to be by-passing about September 1981.
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UNITED STATES
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EDO PRINCIPAL CORRESPONDENCE CONTROL.
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FROM:
DUE: 02/20/87
EDO CONTROL: 002513
DOC DT:~01/30/87'
REP. GERRY E.
STUDDS
FINAL REPLY:-
.TO:
KAMMERER
FOR SIGNATURE OF:
GREEN
SECY NO: 87-85
EXECUTIVE DIRECTOR
DESC:
ROUTING:
ENCLOSES LETTER FROM HOWARD E. SHETTERLY RE
DENTON
WITHHOLDING OF INFO FROM PUBLIC RE' PILGRIM
TAYLOR
NORRY
DATE: 02/05/87
ASSIGNED TO: RI;
CONTACT: MURLEY
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SPECIAL INSTRUCTIONS OR REMARKS:
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OFFICE OFlTHEISECRETARY-
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CORRESPONDENCE CONTROL-TICKET-
iPAPER NUMBER:
-CRC-87-0085
LOGGING-DATE: Feb
3 87
. ACTION.. OFFICE:
' AUTHOR:
G.E. Studds--Const Ref
.l AFFILIATION:-
U.S. HOUSE:OF REPRESENTATIVES
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LETTER DATE:
Jan 30 87-
FILE CODE: C&R-2 BP-
. SUBJECT:
The availability of documents to the'public
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Direct Reply.
ACTION:-
DISTRIBUTION:
OCA to Ack
-: SPECIAL HANDLING: 'None-
. NOTES:.
.Howard E. Shetterly
DATE DUE:
Feb-19 87.
SIGNATURE:
DATE SIGNED:
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