ML20041C148

Proposed Tech Spec Changes,Revising Reporting Levels for Radioactivity Concentration in Environ Samples & Removing Requirement for Automatic Initiation of Control Room High Efficiency Air Filtration Sys

ML20041C148
Person / Time
Site:	Pilgrim
Issue date:	02/23/1982
From:	BOSTON EDISON CO.
To:
Shared Package
ML20041C145	List: ML20041C144 ML20041C148
References
NUDOCS 8202260266
Download: ML20041C148 (11)

Text

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I PROPOSED TECHNICAL SPECIFICATION CHANGE Referencea) Letter from B.K. Grimes, Assistant for Engineering and Projects, USNRC to all Boiling Water Reactor Licensees, dated July 11, 1978.

Proposed Change Reference is made to Pilgrim Nuclear Power Station Unit #1 Technical Specifi-cation Appendix A, Section 6.9 " Reporting Requirements", Item 6.9.C.2.b

" Environmental Program Data". Replace the present Item 6.9.C.2.b with . . .

b. The following event shall be the subject of a written report to the Director of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation) within 60 days of the occurrence of the event: measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of-Table 6.9.C-1 when averaged over any -calendar quarter sampling period.

When more than one of the radionuclides in Table 6.9.C-1 are detected above lower limits of detection (LLD) in the sampling medium, this report shall be submitted if:

Concentration [1) , Cor.centrction -(2) + * * * > 1. 0 Limit Level (1) Limit Level (2) -

When radionuclides other than those in Table 6.9.C .1 are de-tected above LLD and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than quarterly and/or yearly limits of Table 6.9.C-2. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition'shall be reported and described in the Annual Radiological Environ-mental Monitoring ' Report.

Add Table 6.9.C-1 " Reporting Levels for Radioactivity Concentrations in Environmental Samples" and Table 6.9.C-2 " Reportable Annual Dose Coninit-ments" as referenced in the above changes and number the'pages 223a and 223b respectfully as shown on pages 223, 223a', and 223b attached.

Reason for Change l The proposed change is in direct response to USNRC's request-(reference a) that Boston Edison amend Pilgrim Station's Operating License.

Safety Considerations The proposed technical specification is intended to implement the following Federal Regulations: NUREG 0473,10 CFR 50 Appendix I.

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8202260266 820223 PDR ADOCK 05000293 P PDR l

u.d i A safety evaluation has been performed for this change and it is not considered to constitute an unrevi,ewed safety question. These changes have been reviewed and approved by the Operations Review Committee and reviewed by the. Nuclear Safety Review and Audit Committee.

Schedule of Chancq This change w r .1 be put into effect upon receipt of approval by 'the Commission.

Fee Determination

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Pursuant to '9 CFR 170.12, Boston Edison proposes this change as a Class II.

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3 D, C. Unicue Reporting Recuirements

=1.. Radioactive Effluent Release Report A' report shallLbe submitted to the Commission within 60' days lafter January,: 1 and July, -1 of each year specifying.the quantity of each of:the. principal radionu' elides' released'to unrestricted areas.in liquid and gaseous effluents during the previous 6 months. -The

-format and' content of the. report shall be in accordance with:

,- . Regulatory, Guide 1.21-(Revision.1) dated June,fl974.-

2. Environmental Program Data

a. Annual' Report. A' report on the radiological. environmental surveillance program for the previous 12: months of operation

.shall be submitted to the Director oflthe NRC Regional Office -

(with a copy to the Director, 0ffice of Nuclear Reactor:

Regulation) as a separate document'within 90.dr s after' January I'of each year. . The reports shall include summaries, interpret-ations, and statistical evaluation of the results of she radio-logical environmentar surveillance activities for.the report

• _ period, including's comparison with preoperational. studies, operational' controls (as appropriate), and previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the-environment. The reports shall also include the results of any land use surveys'which affect the choice of sample locations. If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the' problem and a preposed course of action to alleviate the. problem.

Results of'all radi$ logical environmental samples shall be summarized and tabulated on an annual br. sis. In the event that i some results are not available within the 90-day period, the report shall be submitted, noting, and explaining the reasons

. for the' missing results. The missing data'shall be submitted as soon as possible in a supplementary report, ,

b. The following event shall be' the subject of. a written report to the 1 Director of the NRC Regional Office (with a copy to the Director, Office of. Nuclear Reactor Regulation) within 60 days of the occur-rence of the event: . measured levels of radioactivity lin an environ-mental sampling medium determined to exceed the reporting level values of Table 6.9.C-1 when averaged over any calendar quarter r

sampling period. When more than one of the radionuclides -in Table i 6.9.0-1 are detected above lower limits of detection (LLD) in the sampling medium, this report shall be submitted if:

Concentration (1) +. Limit Concentration Level (2)

(2) + . . . g .0 Limit Level (1) l' When radionuclides other than those in Table 6.9.C-1 are detected-

'above LLD and are the result of plant effluents, this report shall be submitted if _ the potential annual dose to an individual is equal to or greater than quarterly and/or yearly limits of Table

6. 9. C-2. This report is not required if the measured level of radioactivity was not the result of _ plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report.

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TABLE 6.9.C-1 ,.

REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIR0PfiENTAL SAMPLES r Reporting Levels Water, Fish, Mussels Milk Vegetables Analysis (pCi/1) AirborneParticu}

or Gases (pCi/M ate-

) (pCi/Kg, wet) (pCi/l) (pCi/kg, wet)

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'H-3 2 k 104 Mn-54 1 x 10 3 3 x 10 4 Fe-59 4 x 10 2 1 x 104 '

Co-58 1 x 10 3 3 x 104 Co-60 .3 x 102 1 x - 10 4'

Zn-65 3 x 10 2 2 x 104 Zr-95 4 x 102

' 2 I-131 '2 0.9 3 1 x.10 Cs-134 30 10 l'x 103 ,

60 1 x 103 '

Cs-137. 50 20 2.x 10 3 70 2 x 103 Ba-140 2 x 102 ,

3 x 102 i

<C Table 6.9.C-2 ','  ;

Reportable Annual Dose Committments . . .

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Pathway Dose Limits Dose to Max (L1.5 nrem total body / quarter Individual due to Liquid Effluents $L 5.0l mrem-to any organ / quarter Dose to Max 6_3.0 mrem total body / year Individual due to Liquid Effluents $L10.0 mrem to any organ / year

.1 Air Dose due to $L 5.0 mrad gamma / quarter Noble Gases 1L 10.0 mrad beta / quarter h Air Dose Due to $L10.0 mrad gamma / year-Not e Gases  !L 20.0 mrad beta / year Dose to Max. $L7.5mremtoanyorgan/ quarter ' '

Individual due to Radiciodines and Particulates Doss to Max fl15.0 mrem to any organ / year Individual due to Radiciodines and Particulates 4 c

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PROPOSED TECHNICAL SPECIFICATION CHANGE Proposed Change:

Reference is made to Pilgrim Nuclear Power Station Operating License No. DPR-35, Table 3.7.1, Primary Containment Isolation Valves, p.162. The purpose of this table is to identify the primary containment isolation valves, their maximum operating time, normal position and action upon an initiating signal.

The Table 3.7.1 currently lists:

(a) Two (2) check valves on the control red hydraulic return line, one inboard and one outboard.

(b) Eighteen (18) outboard valves in the Oxygen Analyzer System.

The desired revision shall remove from the list:

(a) The two (2) check valves on the control rod hydraulic return line.

(b) Two (2) of the eighteen (18) outboard valves in the Oxygen Analyzer System.

Reason for Change:

Check Valve CV 301-95 has been cut and capped as a result of the removal of the 3" Control Rod Drive bypass line (Ref. BE0o Ltr. #82-22, dated 1/19/82).

NUREG 0619 allows the CRD line to be cut and capped provided the alternate path to the vessel through the seals provides an adequate flow path. The second valve listed had been capped in a previous design change.

The two aforementioned valves in the Oxygen Analyzer System must be removed l to implement the C-19 Panel modification.

Safety Consideration:

The proposed Technical Specification Changes presents no unreviewed safety question according to 10CFR50.59(c). It has been reviewed and approved by the Operations Review Committee (ORC), and reviewed by the Nuclear Safety Review and Audit Committee (NSRAC).

Schedule of Change:

This change will be put into effect upon BEco's receipt of approval by the Commission.

Fee Determination:

BECo has determined that this change is subject to a Class III fee of $4,000.00.

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t-e' TABI.b a.7.1 PRIMARY CONTA1TIMENT ISOTATION VAINES .h .

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- Ntunber of Power Maximum Groun Operated Valves.. Operating Action on~

Vnive Identification Inboard- Outboard Normal Initiating.

Tiw.e (nec.) Positi_on ,_ S t .a,na,l_

Feedwater check valves 2 2 NA 0 Process 1

l 2 Oxygen Analyzer System

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y. O Gc i i Standby liquid control system j- check valves s 1 1 NA c 4 Procese 3 RHRS. shutdown cooling suction isolation valves- 1 1 30 c sc 3* Rims shetdown cooling injection t

isolation valves 2 30 c sc

! l 3 Reactor vessel head spray isola-tion valves 1 1 30 c sc 2 .

Rims discharge isolation valves .

to radt:nsto 1 1 20

' c Sc la ,

lirCE: stema line isolution valvet 1 1 25 0 GC Il llPCIS torus suc ion isolation valves 2 30 c sc 5

RcIcS steam 13- isolation valves 1 1 20

0 cc-g 6 Reactor wate: rieanup system g isolation val t 1 1

! 25 0 GC 6 Reactor water e .canup system retttrn isolatie a valve 1.

30 O cc 2 Drywell equipme t drain dischar(y isolation valves a 3 0 cc ,

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Proposed Technical Specification Change l . Proposed Change

" Reference.is made to Pilgrim Nuclear Power Station, Unit #1 Technical Specification

, Appendix A, Section 4.5.E " Automatic Depressurization System-(ADS)" Surveillance Requirements. Item 4.5.E.1.a surveillance requirement states that a. simulated automatic actuation ~ test of the ADS be performed from the. Alternate Shutdown Station. This surveillance should be changed to Item 4.5.E.1.c, which require's manual operation.of each relief valve solenoid. This test will be per-formed after each refueling outage prior to start-up. (Example shown on Page 109 attached).

Reason for Change A simulated a'utomatic actuation test of ADS is not possible from the Alternate Shutdown Station. The purpose of the Alternate Shutdown Station for ADS is to

, be able to operate each relief valve manually in case of a fire and safe shut-down is required.. This change clarifies the intent and capabilities of the i alternate shutdown station which were erroneously catalogued through an admin-l istrative error associated with Amendment 42.

Safety Considerations

l. This change has already been addressed in Amendment 42. and does not present any unreviewed safety questions. These changes have been reviewed and approved by the Operations Review Committee and reviewed.by the Nuclear Safety Review and Audit Committoe.

Schedule of Change

[ This change will be put into effect upon receipt of approval by the Commission.

Fee Determination l

Pursuant to 10 CFR Section 170.12, Boston Edison proposes this change as a .

Class II.

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I.T.VITING CONDITION Knt Urravu ava 'wwo.--- - - - -

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~~3 5.D 'Reacter' Care'I: elation Coolinc- 4.5.D Reactor Core isolatt en Ceating .

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(RCIC) Subsystem (C:nt'd) (RCIC) Sub:ystem (Cant'd) 4

d. Tiow Rate at once/3 month:

1000 psig

e. Flow Rate-at- Once/ operating 150 psig eyele The RCIC pump chall deliver at

. ' 1 cast 400 sp: for a sy:tes head .

corresponding to a reactor pres-sure of 1000 to 150 psig

2. From and after the date that the 2. When it is determined that the RCIC RCICS is made or found to be inop- subsystem is inoperable, : the EPC*G erable for any reason, continued shall be de=onstrated to be operable reactor power operation is yer=is- ic=ediately and veekly thereafter.

sible only during the succeedin6 *

. . seven days provided that during such seven days the hPCIS is oper-able.

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3. If the requirements of 3.5.D -cannot be net, an orderly shutdown shall -

be initiated and the reactor pres-

, sure'shall be reduced to or belov 104 psig within 24' hours.

3 5.E Auto stic Depressurization 4.5.E Auto atie Depressurization System (ADS) System (ADS)

1. The Automatic Depressurization Sub- 1. Daring each operating cycle the system shall be operable whenever following tests shall be perforced there is irradiated fuel in the - on the ADS:

reactor vessel and the reactor pres-rure is greater than 104 psig and

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a. A siculated auto:stic cerus-ion prior to a startup from a Cold Con- test shall be perfor:ed prier to dition, except as specified in startup after each refueling occ-3 5.E.2 below. age.

b. With the reactor at pressure, i

( each relief valve shall be man-ually opened until a corresponding change in reactor pressure or main

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l turbine bypass valve positions indicate that steam is flowine from the valve A=endment No.

c.

Perform a test from the alternate shutdown panel to verify that the

- relief valve solenoids actuate.

Test shall be performed after each refueling outage prior to startup.

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s Proposed Technical Specification Change Proposed Change Reference is made to Pilgrim Nuclear Power Station, Unit #1, Amendment 42, Section 4.7.B.c.(1) on Page 158c.

- This section currently states:

c. At least once every 18 months the following shall be demonstrated:

(1) Automatic initiation of the control room high efficiency air filtration system.

The proposed change consists of removing this section in it's entirety.

Reason for Change This change allows the referenced Technical Specification to conform to actual -

plant conditions. The Control Room High Efficiency Air Filtration System is not designed to be actuated automatically, and is strictly a-manually actuated system. This Technical Specification is-in error by requiring a demonstration of a condition that cannot be obtained by design, and cannot be accomplished.

The desired testing on this systems occurs on a monthly basis via Specification 4.7.B.2.b.(4).

Safety Considerations This change represents word changes to effect a closer correspondence between the referenced Technical Specification and the actual operation of the system-as designed; therefore, this change poses no unresolved safety considerations as defined in 10 CFR, Part 50.59(c).

This change has been reviewed and approved by the Operations Review Comnittee and reviewed by the Nuclear Safety Review and Audit Committee.

Schedule of Change This change shall become effective when receipt of the Commission's approval is received.

Fee Determination Pursuant to 10 CFR 170.12, Boston Edison proposes this change as a Class II.

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.- s 3.7.B -(Continued) 4.7.B (Continued) d > ' . shutdown shall be c. At least cnce every 18 months

. initiated and the reactor the following shall be shall be in cold shutdown demonstrated:

within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and irradiated fuel haad11ng operations shall be terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (Fuel handl-ing operations in progress may be completed).

(1) Operability of heaters

d. Fans shall operate within at rated power.

l + 10% of 1000 cfm.

3. Perform an instrument functional test on the hmnidistate controlling the heaters.

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158C

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