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#REDIRECT [[IR 05000289/1984035]]
{{Adams
| number = ML20140D247
| issue date = 12/10/1984
| title = Insp Rept 50-289/84-35 on 841107-09.No Violations Noted. Major Areas Inspected:Actions & Status Re Open Items Identified in Previous Insps
| author name = Shanbaky M, White J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| addressee name =
| addressee affiliation =
| docket = 05000289
| license number =
| contact person =
| document report number = 50-289-84-35, NUDOCS 8412180385
| package number = ML20140D242
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 4
}}
See also: [[see also::IR 05000289/1984035]]
 
=Text=
{{#Wiki_filter:.
. .
                            U.S. NUCLEAR REGULATORY COMMISSION
                                          REGION I
    Report No.  50-289/84-35
    Docket No.  50-289
    License No. DPR-50                Priority    --
                                                            Category      C
    Licensee: GPU Nuclear Corporation
                Post Office Box 480
                Middletown, Pennsylvania    17057
    Facility Name: Three Mile Island Nuclear Station, Unit 1
    Inspection At: Middletown, Pennsylvania
    Inspection Conducted: November 7-9, 1984
    Inspectors:
                  J.
                      [                    f                        /2 !da      9 b'
                      ? White, Senior Radiation Specialist              'da te '
    Approved by:  #Y,            4. IM/                          /2 /4 ff
                  M. M. Shanbaky', Chief /                            'dat'e
                  PWR Radiation Safety Section
    Inspection Summary:
    Inspection Conducted on November 7-9, 1984 (Report No. 50-289/84-35
    Areas Inspected:    Routine, unannounced inspection of the licensee's actions and
    status relative to open items identified in previous inspections. The inspec-
    tion involved 24 hours on-site by one region-based inspector.
    Results: Of the eight items reviewed, five were verified as completed.            No
    violations were identified.
              8412180385
                DR ADOCK 05        8 h h9
                                  PDR
 
. ,
                                        DETAILS
    1. Persons Contacted
      During the course .of this inspection the following personnel were
      contacted.or interviewed:
      *R. Knight, Licensing Engineer, TMI-I
      *J. Whitehead, Emergency Planner
      *G. Baker, Manager - Environmental Controls
      *B. Good, Radiological Programs Manager
      *J. Byrne, Manager, TMI-2 Licensing
      *J. Auoer, Licensing Engineer, TMI-2
      * Denotes attendance at the Exit Interview on November 9, 1984.
      Other members of the licensee's staff and GPU Nuclear Corporation were
      also contacted during this inspection.
    2. Purpose
      The purpose of this inspection was to verify the licensee's completion of
      various open items identified in previous inspections and to determine the
      status of those items yet to be completed.
    3. Status of Previously Identified Items
      3.1 (0 pen) Inspector Follow-up Item (289/83-20-03): Evaluation of the
            effect of a temperature increase on the response of the RM-L-10
            turbine building sump radiation monitor.
            Since the licensee has not /et qualified or quantified the effect of
            temperature on the monitoring device, efforts were initiated to re-
            view the operating procedure and reduce the alarm set point suf-
            ficiently to offset instrument abnormalities that may be due to sump
            temperature.    The licensee committed to complete the action by
            December 15, 1984.    Further, the licensee committed to collect and
            analyze sump temperature data for six months following plant start-up
            to verify that sump temperatures did not exceed the instrument's per-
            formance specifications. This item will remain open until sufficient
            information is available to conclude that the instrument will perform
            acceptably in the normal turbine sump environment.
      3.2 (0 pen) Inspector Follow-up Item (289/84-03-01):          Provide the
            capability to obtain an RCS sample under all accident conditions and
            modes of operation.
            The licensee is in the process of completing system modification to
            permit sampling from the Decay Heat System. Modifications were ex-
            pected to be completed by November 17, 1984, followed by pre-opera-
            tional and start-up testing in the following six weeks. This item
                                                                                  I
                                          -- -            --    .
 
_.
      +    +
                                                                                                                l
                                                  3'
                  will remain open until the start-up testing program for the modifi-
                  cation has been successfully completed.                                                      l
            3.3 (Closed) Inspector Follow-up Item (289/84-03-02): Modify Containment
                  Atmosphere Sampling (CAS) System to permit sampling after containment
  --  --
                  isolation; evaluate sample representativeness and make provisions to
                  assure that temperature and pressure corrections are considered.
                  EPIP 1004.31, " Post Accident Atmospheric Sampling" has been revised
                  to  address design changes in the CAS System and includes
                  consideration of temperature and pressure in the evaluation of sample
                  results. The CAS system has been modified to enable the acquisition
                  of a more reliable and representative sample. The licensee has
                  verified system operability.        Override capability is provided to
                  enable sample acquisition if required following automatic containment
                  isolation. This item is considered closed.
            3.4 (Closed) Inspector Follow-up Item (289/84-03-05): Provide results of
                  demonstration of chemical. analysis capability for chloride, boron and
                  pH using the intended post accident instrumentation and procedures.
                  The licensee's submittal dated February 29, 1984 provided the results
                  of a demonstration of ability to analyze a post accident standard
                  test matrix solution.      While most chemical parameter results were
                  acceptable, it was identified that the use of the Flouroborate
                  Specific Ion Electrode technique, Procedure CP-N1904.1, provided
                  unacceptably high errors for boron concentrations greater than 500
                  ppm.    In order to assure acceptable results, the licensee's program
                  now relies on the Mannitol Boron technique, Procedure CP-N1904, for
                  concentrations greater than 500 ppm. Procedure CP-N1901.1 is only
                  used for concentrations less than 500 ppm boron.
                  Additionally, the licensee's Emergency Plan Implementing Procedure
                  1004.33, Revision 7, " Post Accident Sample Analysis", now addresses
                  the analysis of fission gases stripped from the coolant sample and
                  incorporates the information into the core damage estimation. TDR
                  No. 494, Revision 2, " Post Accident Sampling Radiological Analysis",
                  addresses the personnel exposure due to acquisition of the stripped
                  gas sample.
                  This item is considered closed.
            3.5 (0 pen) Inspector Follow-up Item (289/84-16-01): Test and balance
                  Auxiliary and Fuel Handling Building Ventilation upon completion of
                  system modifications.
                  System modifications are not expected to be completed until April 1,
                  1985.    This item will remain open until test and balance data has
                  been reviewed.
                                              n
                                -          -        -~    -    -      .,    ~ , . - , . - - . , , - - . - , .
 
o
  . . , , .
                          .
                                                    4
                3.6L(Closed) Inspector Follow-up Item (289/84-16-02):              Review process
                      control procedure to assure that the requirements of 10 CFR 61.55 and
                      61.56 are sufficiently addressed.
                      It was verified that Procedures 1104-28A and 1104-28I are both being
                      implemented and subject to-audit by the quality assurance ' group.
                      Quality Assurance Monitoring Reports Nos. SLS-0335-84, DMW-288-84,'
                      SJH-1015-84, DHW-308-84 and SCD-1254-84 were reviewed and substan-
                      tiate that the requireme'nts of 10 CFR 61.55 and 61.56 are being              '
                      implemented in the process control program.
              -3.7  (Closed) Inspector Follow-up Item (289/84-16-03): Review licensee's
                      response to IE Report 50-320/84-04 relative to ALARA effectiveness.
                      This item is closed with respect to Unit-1. The licensee's response
                      will be evaluated relative to Unit-2 ALARA effectiveness.
                3.8 (Closed) Inspector Follow-up Item (289/84-03-07): Develop procedures
                      for the collection of representative plant effluent samples including
                      provisions for handling and analyzing high dose rate samples.
                      In order to reduce dose effect on personnel, the licensee modified
                      the existing MAP-5 system by not initially loading Channel #1 with
                      charcoal and particulate filters.            Following confirmation of the
                      extent of activity from the fractional collectors (channels #2 and
                      #3), it will be determined if Channel #1 may be used as the primary
                      sample collector.
                      Applicable procedures, such as EPIP 1004.31 " Post Accident
                      Atmospheric Sampling", and associated N1990 Chemistry procedures have
                      been revised as necessary to accommodate the acquisition and analysis
                      of the sample. Special sample geometrics have been established for
                      counting equipment and the capability has been established for pulse
                      pile-up rejection (PUR) circuits in the associated MCAs. The PUR
                      circuit permits high count rate pulses to be resolved with correction
                      to dead time, and minimal increase in the counting error. This item
                      is considered closed.
            4.  Exit Interview
                The inspectors met with the licensee's representative (denoted in section
                1.0) at the conclusion of the inspection on November 9,1984. The inspec-
                tor summarized the purpose and scope of the inspection and identified
                findings as described in this report.            .
                At no time during the inspection was written material provided to the
                licensee by the inspectors.
                                                  -      - - - _ _      .    .    .  .          -
}}

Latest revision as of 15:40, 27 October 2020

Insp Rept 50-289/84-35 on 841107-09.No Violations Noted. Major Areas Inspected:Actions & Status Re Open Items Identified in Previous Insps
ML20140D247
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/10/1984
From: Shanbaky M, Jason White
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20140D242 List:
References
50-289-84-35, NUDOCS 8412180385
Download: ML20140D247 (4)


See also: IR 05000289/1984035

Text

.

. .

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-289/84-35

Docket No. 50-289

License No. DPR-50 Priority --

Category C

Licensee: GPU Nuclear Corporation

Post Office Box 480

Middletown, Pennsylvania 17057

Facility Name: Three Mile Island Nuclear Station, Unit 1

Inspection At: Middletown, Pennsylvania

Inspection Conducted: November 7-9, 1984

Inspectors:

J.

[ f /2 !da 9 b'

? White, Senior Radiation Specialist 'da te '

Approved by: #Y, 4. IM/ /2 /4 ff

M. M. Shanbaky', Chief / 'dat'e

PWR Radiation Safety Section

Inspection Summary:

Inspection Conducted on November 7-9, 1984 (Report No. 50-289/84-35

Areas Inspected: Routine, unannounced inspection of the licensee's actions and

status relative to open items identified in previous inspections. The inspec-

tion involved 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on-site by one region-based inspector.

Results: Of the eight items reviewed, five were verified as completed. No

violations were identified.

8412180385

DR ADOCK 05 8 h h9

PDR

. ,

DETAILS

1. Persons Contacted

During the course .of this inspection the following personnel were

contacted.or interviewed:

  • R. Knight, Licensing Engineer, TMI-I
  • J. Whitehead, Emergency Planner
  • G. Baker, Manager - Environmental Controls
  • B. Good, Radiological Programs Manager
  • J. Byrne, Manager, TMI-2 Licensing
  • J. Auoer, Licensing Engineer, TMI-2
  • Denotes attendance at the Exit Interview on November 9, 1984.

Other members of the licensee's staff and GPU Nuclear Corporation were

also contacted during this inspection.

2. Purpose

The purpose of this inspection was to verify the licensee's completion of

various open items identified in previous inspections and to determine the

status of those items yet to be completed.

3. Status of Previously Identified Items

3.1 (0 pen) Inspector Follow-up Item (289/83-20-03): Evaluation of the

effect of a temperature increase on the response of the RM-L-10

turbine building sump radiation monitor.

Since the licensee has not /et qualified or quantified the effect of

temperature on the monitoring device, efforts were initiated to re-

view the operating procedure and reduce the alarm set point suf-

ficiently to offset instrument abnormalities that may be due to sump

temperature. The licensee committed to complete the action by

December 15, 1984. Further, the licensee committed to collect and

analyze sump temperature data for six months following plant start-up

to verify that sump temperatures did not exceed the instrument's per-

formance specifications. This item will remain open until sufficient

information is available to conclude that the instrument will perform

acceptably in the normal turbine sump environment.

3.2 (0 pen) Inspector Follow-up Item (289/84-03-01): Provide the

capability to obtain an RCS sample under all accident conditions and

modes of operation.

The licensee is in the process of completing system modification to

permit sampling from the Decay Heat System. Modifications were ex-

pected to be completed by November 17, 1984, followed by pre-opera-

tional and start-up testing in the following six weeks. This item

I

-- - -- .

_.

+ +

l

3'

will remain open until the start-up testing program for the modifi-

cation has been successfully completed. l

3.3 (Closed) Inspector Follow-up Item (289/84-03-02): Modify Containment

Atmosphere Sampling (CAS) System to permit sampling after containment

-- --

isolation; evaluate sample representativeness and make provisions to

assure that temperature and pressure corrections are considered.

EPIP 1004.31, " Post Accident Atmospheric Sampling" has been revised

to address design changes in the CAS System and includes

consideration of temperature and pressure in the evaluation of sample

results. The CAS system has been modified to enable the acquisition

of a more reliable and representative sample. The licensee has

verified system operability. Override capability is provided to

enable sample acquisition if required following automatic containment

isolation. This item is considered closed.

3.4 (Closed) Inspector Follow-up Item (289/84-03-05): Provide results of

demonstration of chemical. analysis capability for chloride, boron and

pH using the intended post accident instrumentation and procedures.

The licensee's submittal dated February 29, 1984 provided the results

of a demonstration of ability to analyze a post accident standard

test matrix solution. While most chemical parameter results were

acceptable, it was identified that the use of the Flouroborate

Specific Ion Electrode technique, Procedure CP-N1904.1, provided

unacceptably high errors for boron concentrations greater than 500

ppm. In order to assure acceptable results, the licensee's program

now relies on the Mannitol Boron technique, Procedure CP-N1904, for

concentrations greater than 500 ppm. Procedure CP-N1901.1 is only

used for concentrations less than 500 ppm boron.

Additionally, the licensee's Emergency Plan Implementing Procedure

1004.33, Revision 7, " Post Accident Sample Analysis", now addresses

the analysis of fission gases stripped from the coolant sample and

incorporates the information into the core damage estimation. TDR

No. 494, Revision 2, " Post Accident Sampling Radiological Analysis",

addresses the personnel exposure due to acquisition of the stripped

gas sample.

This item is considered closed.

3.5 (0 pen) Inspector Follow-up Item (289/84-16-01): Test and balance

Auxiliary and Fuel Handling Building Ventilation upon completion of

system modifications.

System modifications are not expected to be completed until April 1,

1985. This item will remain open until test and balance data has

been reviewed.

n

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

o

. . , , .

.

4

3.6L(Closed) Inspector Follow-up Item (289/84-16-02): Review process

control procedure to assure that the requirements of 10 CFR 61.55 and

61.56 are sufficiently addressed.

It was verified that Procedures 1104-28A and 1104-28I are both being

implemented and subject to-audit by the quality assurance ' group.

Quality Assurance Monitoring Reports Nos. SLS-0335-84, DMW-288-84,'

SJH-1015-84, DHW-308-84 and SCD-1254-84 were reviewed and substan-

tiate that the requireme'nts of 10 CFR 61.55 and 61.56 are being '

implemented in the process control program.

-3.7 (Closed) Inspector Follow-up Item (289/84-16-03): Review licensee's

response to IE Report 50-320/84-04 relative to ALARA effectiveness.

This item is closed with respect to Unit-1. The licensee's response

will be evaluated relative to Unit-2 ALARA effectiveness.

3.8 (Closed) Inspector Follow-up Item (289/84-03-07): Develop procedures

for the collection of representative plant effluent samples including

provisions for handling and analyzing high dose rate samples.

In order to reduce dose effect on personnel, the licensee modified

the existing MAP-5 system by not initially loading Channel #1 with

charcoal and particulate filters. Following confirmation of the

extent of activity from the fractional collectors (channels #2 and

  1. 3), it will be determined if Channel #1 may be used as the primary

sample collector.

Applicable procedures, such as EPIP 1004.31 " Post Accident

Atmospheric Sampling", and associated N1990 Chemistry procedures have

been revised as necessary to accommodate the acquisition and analysis

of the sample. Special sample geometrics have been established for

counting equipment and the capability has been established for pulse

pile-up rejection (PUR) circuits in the associated MCAs. The PUR

circuit permits high count rate pulses to be resolved with correction

to dead time, and minimal increase in the counting error. This item

is considered closed.

4. Exit Interview

The inspectors met with the licensee's representative (denoted in section

1.0) at the conclusion of the inspection on November 9,1984. The inspec-

tor summarized the purpose and scope of the inspection and identified

findings as described in this report. .

At no time during the inspection was written material provided to the

licensee by the inspectors.

- - - - _ _ . . . . -