ML20059D162

Amend 48 to License DPR-73,extensively Modifying TMI-2 App a & B TSs Consistent W/Plans for post-defueling Monitoring Storage of Facility

ML20059D162
Person / Time
Site:	Crane
Issue date:	12/28/1993
From:	Weiss S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20059D157	List: ML20059D154 ML20059D162 ML20059D177
References
NUDOCS 9401070040
Download: ML20059D162 (54)

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_ UNITED STATES -

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WASHINGTON. D.C. 2DgEMIO01

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GPU NUCLEAR CORPORATION DOCKET NO. 50-320 -

THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 2' POSSESSION ONLY LICENSE

-Amendment No.-48 License No.'DPR 1.

The U.S. Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment filed by ~GPU Nuclear Corporation (ths.

licensee) dated August 16, 1988, as supplemented by submittals dated September 19, 1988,: February 9,1989, March 31,1989, June 26,1989, October 10, 1989, November 22, 1989, June 21, 1990, October 15,-1990,.

November 7, 1990, February 19, 1991, April 19, 1991, June 21, 1991, August 28, 1991, October 9, 1991, January 13, 1992, January 18,1993, May 28, 1993, October 24, 1993, and November 12,.1993, complies with the standards and requirements of the Atomic Energy Act of 1954,:as amended (the Act), and the regulations of the Comission'as set forth in 10 CFR Chapter I; B.

The facility will be maintained in conformity with the application,.

the provisions of the Act, and the rules and regulations.of the.

Ctmission; C.

There is reasonable assurance (i) that the-activities authorized by.

this amendment can be conducted without endangering-the health and safety of the public, and (ii) that such activities will be conducted-1 in compliance with the regulations of the Comission; D.

The issuance of this amendment will not be inimical to the_ comon.

defense and security or to the health and safety of the public;;4nd E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of-l the regulations of the Commission and all applicable' requirements have been satisfied.

9401070040 931228 PDR ADOCK 05000320 P

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qp ?- 2. ;Accordingly, the license.is: amended by changes to the Technical Specifications as indicated'in the enclosure to this-license amendment, and paragraph 2.C(1) of Possession Only License No. DPR-73 is hereby amended to read as follows:

(1) Technical Soecifications The Technical Specifications, as revised through Amendment No. 48, are hereby incorporated into this-license. The licensee shall.

maintain the facility in accordance with the Technical. Specifications and all Commission Orders issued subsequent Lto the date of the!

possession only license.

3.

This license amendment is effective as of the date of~ issuance.

FOR THE NUCLEAR REGULATORY COMMISSION-

,j Seymour H. Weiss, Director.

i Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactor. Support j

Office of Nuclear Reactor Regulation; Enc 1osure:

. Technical Specifications

.Date of issuance: December 28, 1993'

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k TECIINICAL SPECIFICATIONS -

FOR

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TABLE OF CONTENTS -

~ DEFINITIONS -

SECTION TITLE PAGE

- I.0 DEFINITIONS 1-1 '

1.1 DEFINED TERMS

--l-l' l.2 POST DEFUELING MONITORED STORAGE 1-1 (j

1.3 ACTION 1-1

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1.4 OPERABLE - OPERABILITY lit i

1.5 CH ANNEL CAllBRATION 1 1.6 CHANNEL CHECK 1-l' l.7 CHANNEL FUNCTIONAL TEST l-1 1.8 FREQUENCY NOTATION 1-2 1.9 CONTAINMENT ISOLATION 1-2 1

1.10 BATt.H RELEASE l-2

1. I 1 CONTINUOUS RELEASE l-2 l.12 OFF SITE DOSE CALCULATION MANUAL

-12.

1.13 REPORTABLE EVENTS 1-3' 1.14 STAGGERED TEST BASIS 1-3 1.15 SUBSTANTIVE CHANGES 1-3 1.16 MEMBER (S) OF THE PUBLIC I-4 1.17

~ UNRESTRICTED. AREA 1-4 1.18 SITE BOUNDARY l i 1.19 NPDES PERMIT l-4.

I TABLE 1.1 FREQUENCY NOTATION 1-5 t

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Amendment 48

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w S AFETY LIMITS -

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TITLE PAGE "t

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' SAFETY LIMITS 2 !

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f' TABLE OF CONTENTS LIMITING CONDITIONS FOR PDMS AND SURVEILLANCE REOUIREMENTS SECTION TITLE PAGE 3/4.d -

APPLICABILITY -

3/4.0-1 3/4.1 CONTAINMENT SYSTEMS 3/4.1-I 3 /4.1.1 PRIMARY CONTAINMENT 3 /4.1 i CONTAINMENT ISOLATION

- 3/4.1-1 y

UNFILTERED LEAK RATE TESTING -

3/4.1-2 CONTAINMENT AIR LOCKS 3/4.1-3 3/4.2-REACTOR VESSEL FUEL 3 /4.2 !

3/4.2.1 REAClOR VESSEL FUEL REMOVAL / REARRANGEMENT 3/4.2-1 3/4.3 CRANE OPERATIONS 3/4.31 3/4.4 SEALED SOURCES 3/4.4-1

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' BASES FOR LIMITING CONDITIONS FOR PDMS AND SURVEILLANCE REOUIREMENTS -

SECTION TITLE PAGE 3/4.0 '

~ APPLICABILITY B3/4.0-1 3/4..!

CONTAINMENT SYSTEMS B'l/4.1-1 3/4.1.1 PRIMARY CONTAINMENT

~ B3/4.1-1 CONTAINMENT ISOLATION B3/4.1 UNFILTERED LEAK RATE TESTING B3/4.1 CONTAINMENT AIR LOCKS B3/4.1-1 3/4.2 REACTOR VESSEL FUEL B3/4.2-1 i

3/4.2.1 REACTOR VESSEL FUEL REMOVAL / REARRANGEMENT B3/4.2-l 3/4.3 CRANE OPERAT10NS B3/4.3 '

3/4.4 SEALED SOURCES B3/4.4-1 f

3/4.4.1 SEALED SOURCE INTEGRITY B3/4.4-1 i

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TABLE OF CONTENTS.

DESIGN FEATURES SECTION TITLE PAGE

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5.0 DESIGN FEATURFS 5-l-

, 5.1 CONTAINMENT

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ADMINISTR ATIVE CONTROLS -

SECTION ^

TITLE

. PAGE 6.0 ADMINISTRATIVE CONTROLS 6-1 t

. 6.1 RESPONSIBILITY 6-1 y

6.2 :

ORGANIZATION 6-1 6.2.1 GPU NUCLEAR ORGANIZATION 6 ;

6.2.2 TMI 2 ORGANIZATION 6-1.

I 6.3.

UNIT STAFF QUALIFICATIONS 6-1 6.4 TRAINING 6-1 6.5 REVIEW AND AUDIT

' 6-2 6.5.1 TECHNICAL REVIEW AND CONTROL

. 6-2 ACTIVITIES 6-2 RECORDS

'6-3 QUALIFICATIONS 6+3 f

6.5.2 INDi. PENDENT SAFETY REVIEW 6-3 s;

t FUNCTION 6-3 RESPONSIBILITIES 6-4 QUALIFICATIONS 6-5 RECORDS 6-5 6.5.3 AUDITS

' 6 l RECORDS 6-6 6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP 6-6 (IOSRG)

FUNCTION 6-6

i ORGANI7ATION 6-6 2!

RESPONSIBILITY -

6 - AUTHORITY

. 6-7 QUALIFICATIONS 6-7

l RECORDS 6-7

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5.6 REPORTABLE EVENT ACTION 6-7 c

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ADMINISTR ATIVE CONTROLS SECTIO.N -

TITLE PAGi?

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. 6.7 PROCEDURES AND PROGRAMS

'6-7 6.8 REPORTING REQUIREMENTS 10 6.8.1 -

ROUTINE REPORTS.

6-10 ANNUAL RADIOLOGICAL ENVIRONMENTAL 6-10 OPERATING REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE 6-10 REPORT ANNUAL REPORTS 6-11 BIENNIAL REPORTS 6-11 6.8.2 SPECIAL REPORTS 6-11 r

6.8.3 NONROUTINE RE' PORTS 6'- l l'

.iy PROMPT REPORTS 6-11 THIRTY DAY EVENT REPORTS 6-11 N

CONTENT OF NONROUTINE REPORTS 6-11 6.9 RECORD RETENTION 6-12 j

6.10 RADIATION PROTECTION PROGRAM 6-14~

6.11 HIGH RADIATION AREA 6-14 6.12 OFFSITE DOSE CALCULATION ' MANUAL (ODCM) 6-14 :

6.13 EXCEPTIONAL OCCURRENCES 15 r

6.13.1 UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS 6-15 6,13.2 EXCEEDING LIMITS OF RELEVANT PERMITS 6-15 6,14 STATE AND FEDERAL PERMITS AND CERTIFICATES

.6-15

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DEFINITIONS t

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e 1.0 ~ DEFINITIONS DEFINED TERMS '

1.1 The DEFINED TERMS-of this section appear in capitalized type and are applicable throughout these Technical Specifications.

POST-DEFUELING MONITORED STORAGE l.2 - POST-DEFUELING MONITORED STORAGE (PDMS) is that condition where TMI-2 defueling has been completed, the core debris removed from the reactor during the cleanup period has been shipped off-site and the facility has been placed in a stable, safe, and secure condition.

ACTION -

1.3 ACTION shall be those additional requirements specified as corollary statements to each specification and shall be part of the specifications.

OPERABLE - OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or. have OPERABILITY when it is capable of performing its specified function (s) and when all necessary-attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

CHANNEL CAL.IBRATION 1.5. - An instrument CHANNEL CALIBRATION is a test, and adjustment, as necessary, to establish that the channel output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values.

CHANNEL CALIBRATION shall encompass the entire channelincluding equipment activation, alarm or trip, and shall be deemed to include the CHANNEL FUNCTIONAL TEST, CH ANNEL-CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.-

CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

Three Mile Island - Unit 2 1-1 Amendment'48 V

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wnw 1.0 ' DEFINITIONS FREOUENCY NOTATION 1.8 The FREQUENCY NOTATION specified for the performance of surveillance requirements shall correspond to the intervals defined in Table 1.1.

CONTAINMENT ISOLATION 1.9 CONTAINMENT ISOLATION shall exist when:

a.

Each penetration is:

1.

Closed by a manual valve, a welded or bolted blind flange, a deactivated automatic valve secured in the closed position or other equivalent ' mechanical closure to provide isolation of each penetration, or 1

2.

Open and the pathway to the environment provided with a HEPA filter, or 3.

Open in accordance with approved procedures. Controls shall be implemented to' minimize the time the penetration is allowed open and to specify the conditions for which the penetration is open. Penetrations shall be expeditiously closed upon completion of the conditions specified in the approved procedures, and b.

The Equipment Hatch is closed, and L

Each Containment Airlock is operable pursuant to Technical Specification 3.1.1.3.

c.

BATCH RELEASE 1.10 A BATCH RELEASE is the discharge of a discrete volume.

CONTINUOUS RELEASE 1.11 A CONTINUOUS RELEASE is the discharge of a non-discrete volume, e.g., from a volume or system that has an input flow during the continuous release.

OFF-SITE DOSE CALCULATION MANUAL 1.12 The OFF-SITE DOSE CALCULATION MANUAL. '(ODCM)' shall contain.the methodology and parameters used in the calculation of off-site doses resulting from radioactive-gaseous and liquid effluents, in the calculation of gaseous and liquid effluent-monitoring-alarm / trip setpoints, and in the conduct of the Rad;ological Environmental Monitoring Program'.

The ODCM shall also contain (1) the programs required by Section 6.7.4 and (2) descriptions-of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.8.1.2 and 6.8.1.3.

I Three Mile Island - Unit 2 1-2 Amendment 48

1.0 DEFINITIONS-REPORTABLE EVENTS 1.13 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 of 10 CFR Part 50.

STAGGERED TEST BASIS i

1. l'4 A STAGGERED TEST BASIS shall consist of:

A test schedule for n systems, subsystems, trains or designated components a.

obtained by dividing the specified test interval into n equal subintervals, b.

The testing of one system, subsystem, train or designated components at the beginning of each subinterval.

SUBSTANTIVE CH ANGES 1.15 SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meaning or intent. Examples of non-substantive changes are: (1)

.i correcting spelling; (2) adding (but not deleting) sign-off spaces; (3) blocking in notes, cautions, etc.; (4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the PDMS Technical Specifications; and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

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t 1.0 DEFINITIONS MEMBER (S) OF THE PUBLIC 1.16 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally-associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

UNRESTRICTED AREA 1.17 An UNRESTRICTED. AREA shall be any area at or beyond th'e SITE BOUNDARY access to which is not controlled by.GPU Nuclear for purposes of protection of individuals from.

- exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, 'nstitutional, and/or recreational purposes.

SITE BOUNDARY 1.18 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by GPU Nuclear. The SITE BOUNDARY for gaseous and.

liquid effluents shall be as shown in the ODCM.

NPDES PERMIT 1.19. The NPDES PERMIT is the National Pollutant Discharge Elimination System (NPDES)-

Permit No. PA0009920, effective January 30, 1975, issued by the Environmental Protection Agency to Metropolitan Edison Company.

This permit authorized Metropolitan Edison Company to discharge controlled waste water from TMI Nuclear Station into the waters of the Commonwealth of Pennsylvania.

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-c e TABLE 1.1

-' i FREOUENCY NOTATION i

k NOTATION FREOUENCY S

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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'V At least once'per 7 days, i

'M At least once per 31 days.

Q At least once per 92 days.

'I SA At least once per 184 days.

A At least once per 12 months.

'R At least once per 18 months.

P Completed prior to each release.

N/A Not applicable.

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e 2.0 SAFETY LIMITS There are no safety limits which apply to TMI-2 during PDMS.

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A SECTION 3/4 LIMITING CONL)ITIONS FOR PDMS AND SURVEILLANCE REQUIREMENTS 3

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'3]_4J LIMITING CONDITIONS FOR PDMS AND SURVEILLANCE REOUIREMENTS 4

3/4.0 APPLICABILITY LIMITING CONDITIONS FOR PDMS 3.0.1 Limiting Conditions for PDMS and ACTION' requirements shall be applicable during POST-DEFUELING MONITORED STORAGE or other conditions specified. for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for PDMS and/or associated ACTION within the specified time interval shall constitute compliance with the specification..

In the event the Limiting Condition for PDMS is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 In the event a Limiting Condition for PDMS and/or associated ACTION requirements cannot be satisfied because of. circumstances in excess of those addressed in the specification, initiate appropriate actions to rectify the problem to the extent possible under the circumstances and submit a report to the Commission pursuant to the requirements of 10 CFR 50.73.

SURVEII LANCE REOUIREMENTS 4.0.1 Surveillance Requirements shall be met during PDMS or other conditions specified for individual Limiting Conditions for PDMS unless otherwise_ stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximum allowable extension not to exceed 25% of the surveillance interval, and b.

A total maximum combined interval time for any four consecutive tests not to exceed 3.25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for PDMS. Exceptions to these requirements are stated in the individual Specifications. Surveillance -

Requirements do not have to be performed on inoperable equipment.

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3/4.1 CONTAINMENT SYSTEMS 3/4.1.1 ' PRIMARY CONTAINMENT CONTAINMENT ISOLATION LIMITING CONDITIONS FOR PDMS 3.1.1.1 Primary CONTAINMENT ISOLATION shall be maintained.

APPLICABILITY: PDMS l

ACTION:

With CONTAINMENT ISOLATION not in accordance with requirements, -restore -

CONTAINMENT ISOLATION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i SURVEILLANCE REOUIREMENTS 4.1.1.1 Primary CONTAINMENT ISOLATION shall be veriGed quarterly with the following exceptions:

Isolation valves that are locked closed shall be verified annually on a quarterly a.

STAGGERED TEST BASIS. If a valve is found to be out of position, a check of all locked closed isolation valves shall be performed.

b.

An independent veri 6 cation of all isolation valve position changes shall be performed.

Bolted or welded blind Dantes which form a containment isolation boundary and the c.

Equipment Hatch shall be visually inspected for signs of degradation and/or leakage every five years on an annual STAGGERED TEST BASIS. If a problem is discovered with a Dange, a check of all bolted or welded blind Danges shall be performed.

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UNFILTERED LEAK RATE TESTING LIMITING CONDITIONS FOR PDMS -

3.1.1.2 The unfiltered leak rate from Containment with the RB Breather closed shall be less than it

_1/100 of the rate through the RB Breather.

t APPLICABILITY: PDMS l

ACTION:

If the unfiltered leak rate from Containment with the RB Breather closed is greater than.1/100' of the rate through the RB Breather or if the trend indicates that the 1/100 value will be exceeded within one year, then:

.. a. Identify the excessive leakage path;

b. Make necessary repairs and/or adjustments; i

c. Perform an additional unfiltered leak rate test; and

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d. Prepare and submit a special report to the Commission pursuant to Specification 6.8.2 within the next 30 days.

i SURVEILLANCE REOlilREMENTS f

4.1.1.2 The initial unfiltered leak rate test shall be performed two years following entry into j

PDMS. After the initial unfiltered leak rate test, the test frequency will be ' determined by comparing the ratios of the unfiltered leak rate to the RB Breather leak rate from previous and current tests. If the test results indicate that the ratio of unfiltered leakage to breather leakage is -

i remaining constant or decreasing, then the next interval shall be five years.

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A SURVEILLANCE REOIIIREMENTS 4.1.1.2_

(con't) -

if the test results indicate that the ratio of unfiltered leakage to breather leakage is increasing, i.e.,

the current ratio is greater than the previous ratio, then the next interval shall be determined by the following equation:

i N' = N X (0. 01 - R ) - 1 y

(R, - R )

p the next test inten'al, where:

N'

=

the current test interval, N

=

the previous ratio of unfiltered leakage to R,

=

RB Breather leakage the current ratio of unfiltered leakage to R,

=

RB Breather leakage The initial value of N shall equal two years. N' shall be the truncated integer result' from the above equation, in years, but not more than five years nor less than one year.

Only ratios for successful tests shall be used to determine 'the next test interval in the above equation. Following a failed test the next test interval shall be one year.

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CONTAINMENT AIR LOCKS IIMITING CONDITIONS FOR PDMS 3.1.1.3 Each Containment Air Lock shall be OPERABLE with at least one door closed except -

l when the air lock is being used for transit entry and exit in accordance~ with site-approved -

procedures.

APPLICABILITY: PDMS ACTION:

1

.With no Containment Air Lock door OPERABLE, restore at least one door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i SURVEILLANCE REOlilREMENTS 4.1.1.3 Each Containment Air Lock shall be demonstrated OPERABLE at least once per three' months by performing a mechanical operability check of each Air Lock Door, including a visual inspection of the components and lubrication if necessary and by visually inspecting the door seals

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for significant degradation. When both Containment Air Lock doors cre opened simultaneously, verify the following conditions:

a.

The capability exists to expeditiously close at least one Air Lock door; j

b.

The Air Lock doors and Containment Purge are configured to restrict the outflow-l of air in accordance with site-approved procedures; and j

c.

.The Air Lock doors are cycled to ensure mechanical operability within seven days.

prior to opening both doors.

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3/4.2 REACTOR VESSEL FUEL l

.3/4.2.-l REACTOR VESSEL FUEL REMOVAL / REARRANGEMENT l

'I IMITING CONDITIONS FOR PDMS '

3.2.1.1 No more than 42 kg of fuel (i.e., UO ) may be removed from the Reactor Vessel without 2

prior NRC approval.

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APPLICABILITY: PDMS ACTION:

When more than 42 kg of fuel has been removed from the Reactor Vessel, suspend all further fuel removal activities and submit a safety analysis to the NRC for approval of this activity and any-further fuel removal activities.

3.2.1.2 No more than 42 kg of fuel in the Reactor Vessel may' be rearranged outside the geometries analyzed in the Defueling Completion Report and the criticality safety 3

analyses contained in GPU Nuclear letter C312-92-2080,_ dated December 18, 1992,'

without prior NRC approval.

APPLICABILITY: PDMS ACTION:

When more than 42 kg of fuel in the Reactor Vessel has been rearranged, suspend all further fuel rearrangement activities and submit a safety analysis to the NRC for approval of this activity and i

any further fuel rearrangement activities. If an external event were to. occur that could potentially cause more than 42 kg of fuel in the Reactor Vessel to be rearranged, a report will be submitted to the NRC detailing the findings of any investigation into that potential rearrangement.

SURVEILLANCE REOUIREMENTS 4.2.1.1 None required as long as no fuel is removed from the Reactor Vessel.

l 4.2.1.2 None required as long as no fuel in the Reactor Vessel is rearranged.

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13/4.3' CRANE OPERATIOJJ 1.!MITING CONDITIONS FOR PDMS' Loa' s'in excess of 50,000 lbs; shall be prohibited from travel over the Reactor Vessel d

3.3.1 unless a docketed Safety Evaluation for the activity is approved by the NRC.

APPLICABILITY: PDMS ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe:

condition and correct the circumstances which caused or allowed the Limiting Condition'for:

PDMS to be exceeded. prior to continuing crane operations limited by. Specification 3.3.1.

Prepare and submit a special report to the Commission pursuant to Specification 6.8.2 within the next 30 days.

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'3/4.3-1 Amedment 48

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3/4.4 SEALED SOURCES 3/4.4.1 SEALED SOURCE INTEGRITY

1.iMITING CONDITIONS FOR PDMS

'T 3.4.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material (except as

.noted in 4.4.1.2) shall be free of 2 0.005 microcuries of removable contamination.

APPLICABLE:

PDMS ACTIO_N:

j a.

Each sealed source with removable contamination in excess of the above limit shall be immediately withdrawn from use and:

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Either decontaminate and repair, or 2.

Dispose in accordance with Commission Regulations.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS TEST REOUIREMENTS i

4.4.1.1 Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or q

b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

TEST FREOUENCIES 4.4.12 Each category of sealed source shall be tested at the frequency described below.

Source in use (excludine fission detectors oreviously subiected to core flux)- At a.

least once per six months for all sealed sources containing' radioactive material:

1.

With a half-life greater than 30 days (excluding Hydrogen 3) and 2.

In any form other than gas.

Tinee r,iile Island - Unit 2 3/4.4-1 Amendment 48

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.r SURVETLi;ANCE REOUIREMENTS i-P b.

Stored sources not in use - Each sealed source and fission de:rctor shall be tested '

prior to use or transfer to another licensee unless tested within the previous six months. Sealed sources and fission detectors transferred without a certificate indicating the last tesJdate shall be tested prior to being placed into use.

c.

Fission detectors - Each sealed fission' detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

REPORTS 4.4.1.3 A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of 20.005 microcuries of removable L

contamination, i

L Three Mile Island - Unit 2 3/4.4-2

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t BASES FOR LIMITING CONDITIONS FOR PDMS AND SURVEILLANCE REQUIREMENTS -

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The summary statements contained in this section l

provide the bases for the Specifications of Section 3.0 and 4.0 and are'not considered a part.

of these Technical Specifications as provided in.

10 CFR 50.36.

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BASES

-The' specifications of this section provide the general requirements applicable to each of the

- Limiting ConGtions for PDMS and Surveillance Requirements within Section 3/4.

j 3.0.1 This specification defines the applicability of each specification in terms of PDMS or other -

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'J specified conditions and is provided to delineate specifically when each yecification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limitmg Condition for PDMS and associated ACTION requirement.

3.0.3 The specification defines the action and reporting requirements for those circumstances where the ACTION statement for Limiting Conditions for PDMS was exceeded.

4.0.1 This specification provides that surveillance ' activities necessary to ensure the Limiting Conditions for PDMS are met and will be performed during the condition for which the Limiting-Conditions for PDMS are applicable.

4.0.2 The provisions of this specification provide allowable tolerances-for : performing surveillance activities beyond those specified in the nominal surveillance interval.

These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.

l The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not degraded beyond that obtained from the nominal specified interval.

4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditiens for PDMS. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this 1

provision is to be construed as defining equipment, systems or components OPERABLE, when E

such items are found or known to be inoperable although s ll meeting the Surveillance.

Requirements.

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.i Three Mile Island - Unit 2 B3/4.0-1 Amendment 48

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3/4.1 CONTAINMENT SYSTEMS BASES 3/4.1.1 PRIMARY CONTAINMENT l

3/4.1.1.1 CO)JTAINKENT ISOLATION CONTAINMENT ISOLATION is maintained to assure the Containment is properly maintained as a contamination barrier for the residual contamination which remains inside the Containment. One barrier either outside or inside of the Containment on each penetration is acceptable. See the PDMS SAR Section 7.2.1.1. Verification of CONTAINMENT ISOLATION is primarily accomplished by visual inspection; however, in cases where this is not practical due to the valve or valves being located in a locked high~

radiation area, documented evidence of the valves closure may be used. Penetrations which have been isolated by chain locked valves provide a high degree of assurance that CONTAINMENT ISOLATION is being maintained and, therefore, require only annual surveillance on a STAGGERED TEST BASIS.

Penetrations which have been closed by bolted or welded blind flanges provide an even higher degree of l

assurance that CONTAINMENT ISOLATION is being maintained and, therefore, require surveillance only every five years also on a STAGGERED TEST BASIS. However, if a valve is found out of position or a problem with a flange is discovered, a complete verification check would be performed to provide assurance that CONTAINMENT ISOLATION is being maintained.

3/4.1.1.2 UNFILTERED LEAK RATE TESTING The Reactor Building fire analysis presented in SAR Section 8.2.5 Case 3 assumes that the mass flowrate of unfiltered leakage is less than 1/100 of the mass flowrate released through the 99% efficient RB Breather HEPA filter. SAR Section 7.2.1.2.3 provides the details of the calculation using an unfiltered

' leak rate test to demonstrate compliance with this Limiting Condition for PDMS. The test interval is variable due to the uncertainty inherent in maintaining the unfiltered leakage to a small fraction of the leakage through the RB Breather.

3/4.1.1.3 CONTAINMENT AIR LOCK _S The Containment Air Locks must be maintained OPERABLE to provide CONTAINMENT ISOLATION.

These air locks will be used during entries into the Containment to ensure that radioactive materials are not unnecessarily being released to the environs. The preferred method for ensuring that radioactive materials are not released during these entries is to maintain at least one door closed at all times; however, if circumstances require, both doors may be open simultaneously in accordance with site-approved procedures.

Three Mile Ishu d - Unit 2 B3/4.1-1 Amendment 48

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3/4.2 REACTOR VESSEL FUEL BASES 3/4.2.1 REACTOR VESSEL FUEL REMOVAL / REARRANGEMENT NRC Inspection Report 50-320/90-03, dated June 14, 1990, imposed restrictions on the removal l

and/or rearrangement of the residual fuel in the Reactor Vessel. In particular, the NRC stated in Section 3.0, " Safe Fuel Mass Limit," of that inspection report that the appropriate safe fuel r.iass limit in the Reactor Vessel (RV) was determined to be 93 kg of core' debris. Based on iniustry practice, a limit of approximately 45% of the SFML was placed on the amount of core debds that may be removed from the RV or rearranged in the RV. This limit is specified to ensure suberiticality even after dual errors. Thus, if the fuel in the RV is rearranged outside the analyzed geometries used in the Defueling Completion Report or the criticality safety analyses contained in GPU Nuclear letter C312-92-2080, dated December 18,1992, the 42 kg limit will apply to the rearranged fuel. Further, if any fuel is removed from the RV in the future, the 42 l

kg limit will also apply to that fuel.

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f Three Mile Island - Unit 2 B3/4.2-1 Amendment 48 I

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3/4.3 CRANE OPERATIONS BASES A load drop into the RV may cause reconfiguration of the core debris outside the analyzed geometries used in the Defueling Completion Report RV criticality analysis.

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Three Mile Island - Unit 2 B3/4.3-1

- Amendment 48

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3/4.4 SEALED SOURCES BASES

-j 3/4.4.l~ SEALED SOURCE INTEGRITY The limitation on removable contamination for sources requiring leak testing, including alpha j

emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from byproduct,- source, and Special Nuclear Material sources will not exceed allowablei intake values.

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r SECTION 5.0 i

DESIGN FEATURES

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5.0 DESIGN FEATURES 5.1 CONTAINMENT

,t CONFIGURATION 4-5.1.1 The Containment Building is a steel lined, reinforced concrete building of cylindrical

.j shape, with a dome roof and having the following design features:

a.

Nominal inside diameter = 130 feet.

b b.

Nominalinside height = 157 feet.

i c.

Minimum thickness of concrete walls = 4 feet.

d.

Minimum thickness of concrete roof = 3.5 feet.

3 4

e.

Minimum thickness of concrete floor pad = 13.5 feet.

f.

Nominal thickness of steel liner = 1/2 inch.

F g.

Net free volume = 2.1 x 106 cubic feet.

h.

Design Pressure = 5.0 psig.

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5 Three Mile Island - Unit 2 5-1 Amendment 48 i

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ADMINISTRATIVE CONTROLS l.

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6.0 ' ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The PDMS Manager is responsible for the management of overall unit operations at Unit 2 and shall delegate in writing the succession to this responsibility during absence.

12 ORGANIZATION GPU NUCLEAR ORGANIZATION 6.2.1 The GPU Nuclear Corporation (GPUNC) organization for unit management and technical support shall be as in Section 10.5 of the PDMS SAR.

TMI-2 ORGANIZATION 6.2.2 The unit organization shall be as described in Section 10.5 of the PDMS SAR and an individual qualined in radiation protection procedures shall be on site whenever Radioactive Waste Management activities are in progress.

6.3 UNIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions unless otherwise noted in the Technical Specifications. The requirements of ANSI N18.1-1971 that pertain to operator license qualifications for unit staff shall not apply.

6.3.2 The management position responsible for radiological control or his deputy shall meet or.

exceed the quali0 cations of Regulatory Guide 1.8 of 1977.

Each Radiological Controls ~

Technician in a responsible position shall meet or exceed the qualifications of ANSI N18.1-1971, paragraphs 4.5.2 or 4.3.2, or be formally qualified through an NRC-approved TMI Radiation Controls training program. All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained and i shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977.-

Three Mile Island - Unit 2 6-1 Amendment 48

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^DMINISTRATIVE CONTROLS i

6.5 - REVIEW' AND AUDIT l

6.5.1 ' TECHNICAL REVIEW AND CONTROL -

1 The Vice President of each division within GPU Nuclear Corporation shall be responsible for ensuring the preparation, review, and approval of documents required by the activities described.-

in Sections 6.5.1.1 through 6.5.1.7 within his functional area of responsibility as assigned in the, GPUN Review and Approval Matrix. Implementing approvals shall be performed at the cognizant -

1 manager level or above.

l ti ACTIVITIES 6.5.1;l Each procedure required by Section 6.7 and other procedures including those for tests and experiments and SUBSTANTIVE CHANGES thereto shall~ be prepared by a designated 1

individual (s) or group knowledgeable in the area affected by the procedure. Each such procedure, and SUBSTANTIVE CHANGES thereto, shall be given a technical review by an individuals (s)-

or group other than the preparer, but who may be from the same organization as the individual!

who prepared the procedure or change.

. 6.5.1.2 Proposed changes to the Technical Specifications shall be reviewed by a knowledgeable individual (s) or group other than the individual (s) or group who prepared the change.

6.5.1.3 Proposed tests and experiments shall be reviewed by a knowledgeable individual (s) or.

l group other than the preparer but who may be from the same division as the individual.who prepared the tests and experiments.

1 6.5.1.4 Proposed modifications to unit structures, systems, and components necessary to maintain the PDMS condition as described -in the PDMS SAR shall be ' designed by -.an l

individual / organization knowledgeable in the areas affected by the proposed modification. Each-

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such modification shall be technically reviewed by an individual / group other than the '

individual / group which designed the modification but may be from the same group as the individual who designed the modification.

6.5.1.5 Investigation of all violations of the Technical Specifications including the preparation.

and forwarding of reports covering evaluation and recommendations to 'revent recurrence, shall be reviewed by a knowledgeable individual (s)/ group other than the individual / group which performed the investigation.

6.5.1.6 All REPORTABLE EVENTS shall be reviewed by an individual / group other than the individual / group which prepared the report.

6.5.1.7 Individuals responsible for reviews performed in accordance'.with Sections 6.5.1.1 through 6.5.1.6 shall include a determination of whether or not additional cross disciplinary.

review is necessary. If deemed necessary, such revievi shall a

i Three Mile Island - Unit 2 6-2 Amendment 48 i

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ADMINISTRATIVE CONTROLS ACTIVITIES (con't)

t be performed by t.he appropriate personnel. Individuals responsible for reviews considered under Sections 6.5.1.1 through 6.5.1.5 shall render determinations in writing with. regard to whether or not 6.5.1.1 through 6.5.1.5 constitute an unreviewed safety question.

BECORDS-6.5.1.'8 Written records of activities performed in accordance with Sections 6.5.1.I' through i

6.5.1.7 shall be maintained in accordance with Section 6.9.

OUALIFICATIONS 6.5.1.9 Responsible Technical Reviewers shall meet or exceed the qualifications of ANSI /ANS --

3.1 of 1978 Section 4.6, or 4.4 for applicable disciplines, or have 7 years of appropriate experience in the field of his or her specialty. Credit toward experience will be given for advanced degrees on a one-to-one basis up to a maximum of two years. Responsible Technical Reviewers shall be designated in writing.

t 6.5.2 INDEPENDENT SAFETY REVIEW FUNCTION 6.5.2.1 The Vice President of each division within GPU Nuclear Corporation shall be responsible for ensuring the independent safety review of the subjects described in Section 6.5.2.5 within his assigned area of review responsibility, as assigned in the GPUN Review and Approval Matrix.

6.5.2.2 Independent safety review shall be completed by an individual or group not having direct responsibility for the performance of the activities under review, but who may be from the same functionally cognizant organization as the individual or group performing the original work.

6.5.2.3 GPU Nuclear Corporation shall collectively have or have access to the experience and competence required to independently review subjects in the following areas:

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a.

Nuclear Unit operations b,

Nuclear engineering c.

Chemistry and radiochemistry

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d.

Metallurgy f

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t Three Mile Island - Unit 2 6-3 Amendment 48 1

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ADMINISTRATIVE CONTROLS FUNCTION (con't) q i

Instrumentation and control e.

f.

Radiological safety g.

Mechanical engineering h.

Electrical engineering i.

Administrative controls and quality assurance practices j.

.Other appropriate fields such as radioactive waste management operations associated with the unique characteristics of TMI-2.

6.5.2.4 Consultants may be utilized as determined by the cognizant Vice President to provide expert advice.

RESPONSIBILITIES 6.5.2.5 The following subjects shall be independently reviewed by Independent Safety Reviewers (ISRs) in the functionally assigned divisions:

3 Written safety evaluations of changes in the facility as described in the Safety Analysis a.

Report, of changes in procedures as described in the Safety Analysis Repon, and of tests or experiments not described in the Safety Analysis Report, which are completed without 7

prior NRC approval under the provisions of 10 CFR 50.59(a)(1). This review is to verify that such changes, tests or experiments did not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2). Such -

review's need not be performed prior to implementation.

l b.

Proposed changes in procedures, proposed changes in.the facility, or proposed tests or experiments, any of which involves a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59(c). Matters of this kind shall be.

reviewed prior to submittal to the NRC.

Proposed changes to Technical Specifications or license amendments shall be reviewed -

c.

prior to submittal to the NRC for approval.

d.

Violations, deviations, and reportable events which require reporting to the NRC in.

writing. Such reviews are performed after the fact. Review of events covered under this subsection shall include results of any investigations made and the recommendations -

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resulting from such investigations to prevent or reduce the probability of recurrence of the event.

Three Mile Island - Unit 2 6-4 Amendment 48 1'l

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" ADMINISTR ATIVE CONTROLS RESPONSIBil_ITIES (con't) e.

Written summaries of audit reports in the areas specified in Section 6.5.3.

f.

Any other matters involving the plant which a reviewer deems appropriate for consideration or which is referred to the mdependent reviewers.

OUALIFICATIONS 6.5.2.6 The ISRs shall either have a Bachelor's Degree in Engineering or the Physical Sciences and five years of professional level experience in the area being reviewed or have nine years of appropriate experience in the field of his or her specialty. An individual performing reviews may possess competence in more than one necialty area. Credit toward experience will be given for advanced degrees on a one-for-one bi.s up to a maximum of two years.

RECORDS 6.5.2.7 Reports of reviews encompassed in Section 6.5.2.5 shall be maintained in accordance with Section 6.9.

6.5.3 AUDITS 6.5.3.1 Audits of unit activities shall be performed in accordance with the TMI-2 PDMS QA Plan. These audits shall encompass:

a.

The conformance of unit operations to provisions contained within the Technical Specifications and applicable license conditions. The audit frequency shall be at least once per 12 months.

b.

The performance of activities required by the PDMS QA Plan. The audit frequency shall be at least once per 24 months.

c.

The Radiation Protection Plan and applicable implementing procedures. The audit frequency shall be at least once per 12 months.

d.

The Fire Protection Program and implementing procedures at least once per 24 months.

An independent fire protection and loss prevention program inspection and e.

technical audit shall be performed annually utilizing either qualified licensee personnel or an outside fire protection firm.

f.

An inspection and audit of the fire protection and loss prevention program by an outside qualified fire consultant at intervals no greater than 3 years.

Three Mile Island - Unit 2 6-5 Amendment 48

' ADMINISTR ATIVE CONTROLS i

6.5.3 AUDITS (con't) g.

The ODCM and implementing procedures at least once per 24 months; h.

. Any other area of unit operation considered appropriate by the PDMS Manager or the Office of the President - GPUNC.

RECORDS 6.5.3.2 Audit reports encompassed by Section 6.5.3.1 shall be forwarded for action to 'the.

f management positions responsible for the areas audited and the IOSRG within 60 days after.

completion of the audit. Upper management shall be informed in accordance with the TMI PDMS QA Plan.

6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP (IOSRG)

FUNCTION 6.5.4.1 The IOSRG shall be a full-time group of engineers, independent of the unit staff, and' located onsite.

ORGANIZATION i

6.5.4.2 a.

The IOSRG staff shall be as specified in the TM1-1 Tech.' Specs. (License No.

DPR-50).

b.

The IOSRG shall report to the director responsible for. nuclear safety assessment and will perform their function for both TMI Unit I and Unit 2.

RESPONSIBILITY 6.5.4.3 The periodic review functions of the IOSRG shall include the following on a selective

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and overview basis:

a.

The independent review activities stated in Section 6.5.2.5 which may be performed after the fact.

I b.

Assessment of unit operations and performance and unit safety programs.

from a nuclear safety perspective.

1 c.

Any other matter involving safe operations of the nuclear power plant that the onsite IOSRG manager or the PDMS Manager deems appropriate for consideration.

1 Three Mile Island - Unit 2 6-6 Amendment 48 i

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' ADMINISTRATIVE CONTROLS AUTHORITY -

6.5.4.4 The IOSRG shall have access to the unit and unit records as necessary to perform its.

evaluations and assessments. Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.

OUALIFICATIONS 6.5.4.5 The IOSRG engineers shall have either: (1) a Bachelor's Degree in Engineering or the Physical Sciences and three years of professional level experience in the nuclear power field including technical supporting functions, or (2) eight years of appropriate experience.in nuclear power plant operations and/or technology. Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.

RECORDS 6.5.4.6 Reports of evaluations and assessments encompassed in Section 6.5.4.3 shall be prepared, approved, and transmitted to the Manager, TMI-2 Department, the division vice president responsible for nuclear safety assessment and the management positions responsible for the areas reviewed.

6,6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The' Nuclear Regulatory Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 to 10 CFR 50, and~

t b.

Each REPORTABLE EVENT shall undergo an independent safety review pursuant to Specification 6.5.2.5 d.

6.7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained for the activities -

necessary to maintain the PDMS condition as described in the PDMS SAR. Examples of these activities are:

a.

Technical Specification implementation.

' b.

Radioactive waste management and shipment.

c.

Radiation Protection Plan implementation.

d.

Fire Protection Program implementation.

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c.

Flood Protection Program implemen'.ation.

Three Mile Island - Unit 2 6-7 Amendment 48 i

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- ADMIN 1STR ATIVE CONTROLS 6.7 PROCEDURES AND PROGR AMS (con't) 6.7.'2 Each procedure required by Section 6.7.1, and SUBSTANTIVE CHANGES thereto, shall be reviewed and approved as described in Section 6.5.1 prior to implementation and shall be -

reviewed periodically as required by ANSI N18.7-1976.

- 6.7.3 Temporary changes to procedures in Section 6.7.1 above may be made provided:

a.

The intent of the original procedure is not altered; b.

The change is approved by two members of the responsible organization qualified in accordance wi h Section 6.5.1.9 and knowledgeable in the area affected by the t

procedure. For changes which may affect the operational status of unit systems or equipment, at least one of these individuals shall be a member of unit management or supervision; and c.,

The change is documented, reviewed and approved as described in Section 6.5.1 within 14 days of implementation.

6.7.4 The following programs shall be established, implemented, and maintained:'

a.

Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control.of 1

radioactive effluents and for maintaining the doses to. MEMBERS OF THE.

PUBLIC from radioactive effluents as low as reasonably achievable.; The-program (1) shall be contained in the ODCM, (2) shall be implemented by.

operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.' The program shall include the following elements:

1.

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in j

accordance with the methodology in the ODCM, 2.

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to-10 CFR Part 20, Appendix B, Table 2, Column 2, 3.

Monitoring, sampling, and analysis of radioactive liquid and gaseous.

effluents in accordance with 10 CFR 20.1301 and with the methodology -

and parameters in the ODCM, l

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.I Three Mile Island - Unit 2 6-8 Amendment 48

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.e ADMINISTR ATIVE CONTROLS i

6.7 PROCEDURES AND PROGRAMS.(con't).

4.

. Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix 1 to 10 CFR Part 50, 5.

Determination of cumulative and projected dose contributions from.

radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6.

Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems -

are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix ! to 10 CFR Part 50, 7.

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 1

8.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE.

BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9.

Limitations on the annual and quarterly doses to a MEMBER OF THE.

PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit'to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50.

b.

Radiolocical Environmental Monitorine Procram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements-of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the. effluent monitoring program. and ~modeling of -

4 environmental exposure pathways. The program shall (1) be contained.in the.

f ODCM, (2) conform to the guidance of Appendix I to'10 CFR Part 50, and (3) include the following:

r Three Mile Island - Unit 2 6-9

- Amendment 48

i ADMINISTR ATIVE CONTROLS 6.7 PROCEDURFS AND PROGRAMS (con't) 1.

Monitoring, ' sampling, analysis, and reporting of - radiation.: and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2.

A Land Use Census to ensure that changes in the use of areas at and ~

beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of the census, and 3.

Participation in an Interlaboratory Comparison Program to ensure that '

independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as-part of the quality assurance program for environmental monitoring.

6.8 REPORTING REOUIREMENTS ROUTINE REPORTS 6.8.1 in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be in accordance with 10 CFR 50.4 unless otherwise noted. Some of the reporting requirements of Title 10, Code of Federal Regulations are repeated below.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.1 The Annual Radiological Environmental Operating Report covering the operation of the unit dusing the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the' results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3,' and IV.C of Appendix 1 to 10 CFR Part 50.

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.2 The Annual Radiological Effluent Release Report covering the operation of the unit-during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix 1 to 10 CFR Part 50.

Three Mile Island - Unit 2 6-10 Amendment 48 -

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ADMINISTR ATIVE CONTROLS

~ 6.8 REPORTING REOUIREMENTS (con't)

ANNUAL REPORTS' 6.8.1.3 Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to i-rch 1 of each year.

Reports required on an annual basis shall include:

a.

A tabulation of the number of station, utility and other personnel (including contractors) for whom monitoring was required, receiving exposures greater than 100 mrem /yr and 2

their associated person-rem exposure according to work and job functions, e,g,,

surveillance, routine maintenance, special maintenance (the dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or' film badge measurements). Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

BIENNIAL REPORTS 6.8,1.4 Biennial reports (i.e., once every two years) covering the activities of the unit as described below during the previous two calendar years shall be submitted prior to March 1 of every other year.

Reports required on a biennial basis shall include:

a.

All changes made to the PDMS SAR during the previous two calendar years.

b.

All changes, tests, or experiments meeting the requirements of 10 CFR 50.59.

SPECIAL REPORTS 6.8.2 Special reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.

6.8.3 NONROUTINE REPORTS A report shall be submitted in the event that an Exceptional Occurrence as specified in Section 6.13 occurs. The report shall be submitted under one of the report schedules described below.

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

This tabulation supplements the requirements of Article 20.2206 of 10 CFR 20.

2 Three Mile Island - Unit 2 6-11 Amendment 48

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ADMINISTR ATIVE CONTROL S 6.8 REPORTING REOUIREMENTS (con't)

PROMPT REPORTS 6.8.3.1 Those events specified as prompt report occurrences shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.

THIRTY DAY EVENT REPORTS 6.8.3.2 Nonroutine events not requiring a promot reoort as described in Subsection 6.8.3.1, shall k

be reported to the NRC either within 30 days of their occurrence or within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to-Sections 401 or 402 of PL 92-500, the Federal Water Pollution Control Act (FWPCA)

{

Amendment of 1972, whichever time duration following the nonroutine event shall result in the earlier submittal.

CONTENT OF NONROUTINE REPORTS 6.8.3.3 Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.

j 6.9 RECORD RETENTION i

6.9.1 The following records shall be retained for at least five years:

a.

Records of sealed source and fission detection leak tests and results.

b.

Records of annual physical inventory of all sealed source material of record.

6.9.2 The following records shall be retained as long as the Licensee has an NRC license to operate or possess the Three Mile Island facility.

[

Records and logs of unit operation covering time interval at each power level.

a.

b.

Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety and radioactive waste systems.

c.

ALL REPORTABLE EVENTS submitted to the Commission.

d.

Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

i Amend' ent 48 Three Mile Island - Unit 2 6-12 m

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7

' ADMINISTRATIVE CONTROLS 6.9-RECORD RETENTION (Con't)

Records of changes made to the procedures required by' Recovery Technical e.

Specification 6.8.1 and PDMS Technical Specification 6.7.1.

q f.

Radiation Safety Program Reports and Quarterly Recovery Progress Reports on the March 28,1979 incident.

g.

Records of radioactive shipments.

h.

Records and logs of radioactive waste systems operations.

i.

Records and drawing changes reflecting facility design modifications made to; systems and equipment described in the Safety Analysis Report, TER, SD, or Safety Evaluation previously submitted to NRC.

j.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup -

histories.

k.

Records of transient or operational cycles for those unit components designed for a limited number of transients or cycles.

1.

Records of reactor tests and experiments.

3 i

Records of training and qualification for current members of the unit staff.

i m.

Records of in-service inspections previously required by the Technical n.

Specifications.

' Records of Quality Assurance activities required by the Operating, Recovery, or j

o.

PDMS Quality Assurance Plans.

p.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

q.

Records of meetings of the Plant Operation Review Committee (PORC) and the Generation Review Committee (GRC), and reports of evaluations prepared by the

{

IOSRG, if applicabl:: to TMI-2.

r.

Records of the incident which occurred on March 28,1979.

s.

Records of unit radiation and contamination surveys.

t.

Records of radiation exposure received by all individuals for whom monitoring

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' was required.

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i Three Mile Island - Unit 2 6-13 Amendment 48 1

e l ADMINISTRATIVE CONTROLS 6.9 RECORD RETENTION (Con't).

u.

Records of gaseous and liquid radioactive material released to the environs.

v.

Records of reviews performed for changes made to the OFFSITE DOSE' CALCULATION MANUAL.

t 6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

6.11 HIGH RADIATION ARFA L

in lieu of the " control device" or. " alarm signal" required by paragraph 20.1601 of 10 CFR 20,-

each high radiation area shall be controlled as specified in the Radiation Protection Plan.

6.12 OFFSITE DOSE CALCULATION MANUAL (ODCM)

SUBSTANTIVE CHANGES to the ODCM:

Shall be documented and records of reviews performed shall'be retained as'-

i a.

required by Specification 6.9.2 v. -.This documentation shall contain:

1.

Sufficient information to support the change together with the appropriate analyses or evaluations j' stifying the change (s) and q

u 2.

A determination that the change will maintain the level of radioactive' l

effluent control required by 10 CFR 20.1301,40 CFR Part 190,- 10 CFRH 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after review and acceptance by GPU Nuclear management.

c.

Shall be submitted to the Commission in the form of a complete, legible copy of-the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM _

was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall-l indicate the date (e.g., month / year) the change was implemented.

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Three Mile Island - Unit 2 6-14.

Amendment 48 -

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ADMINISTR ATIVE CONTROLS

-6.13 EXCEPTIONAL OCCURRENCES

. ' UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS 6.13.1 Any occurrence of an unusual or imponant event that causes or could potentially cause significant environmental impact causally related with station operation shall be recorded and reported to the NRC per Subsection 6.8.3.1.

The following are examples of such events:

excessive bird impaction events on caoiing tower structures or meteorological towers (i.e., more than 100 in any one day); onsite plant or animal disease outbreaks; unusual mortality of any species protected by the Endangered Species Act of 1973; fish kills near or downstream of the site.

EXCEEDING LIMITS OF RELEVANT PERMITS 6.13.2 Any occurrence of exceeding the limits specified in relevant permits and certificates-issued by other Federal and State agencies which are reportable to the agency which issued the permit shall be reported to the NRC in accordance with the provisions of Subsection 6.8.3.2.

This requirement shall apply only to topics of National Environmental Protection Act (NEPA) concern within the requirements of the permits and certificates noted in Section 6.14.

6.14 STATE AND FEDERAL PERMITS AND CERTIFICATES Section 401 of PL 92-500 requires any applicant for a Federal license or permit to conduct any activity which may result in any discharge into navigable waters to provide the licensing agency a certification from the State having jurisdiction that the discharge will comply with applicable provisions of Sections 301,302,306, and 307 of the FWPCA. Section 401 of PL 92-500 further requires that any certification provided under this section shall set forth any effluent limitations and other limitations, and monitoring requirements necessary to assure that any applicant for a.

Federal license or permit will comply with the applicable limitations. Certifications provided in accordance with Section 401 set forth conditions on the Federal license or permit for which the 1

certification is provided. Accordingly, the licensee shall comply with the requirements set forth

.i in the 401 certification dated November 9,1977 or its currently applicable revision, issued to the licensee by the Pennsylvania Department of Environmental Resources, which requires, among other things, that the licensee comply with effluent limitations stipulated in the NPDES PERMIT.

Three Mile Island - Unit 2 6-15 Amendment 48

h ADMINISTR ATIVE CONTROLS

- 6.14 STATE AND FEDERAL PERMITS AND CERTIFICATES (con't)

Changes or addition to the required Federal and State permits and certificates for the protection of the environment noted in this subsection shall be reported to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits or values stipulated in any certification or permit issued pursuant to Sections 401 and 402 of PL 92-500, NRC shall be notified concurrently with the authorizing agency. The notification to'the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.

If, during NRC's review of the proposed change, it is determined that a potentially severe environmental impact could result from the change, the NRC will consult with the authorizing agency to determine the appropriate action to be taken.

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1 Three Mile Island - Unit 2 6-16

. Amendment 48

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