ML20092J133

Amend 72 to License NPF-58,revising TS Consistent W/Gl 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to ..

ML20092J133
Person / Time
Site:	Perry
Issue date:	09/15/1995
From:	Hopkins J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20092J136	List: ML20092J133 ML20092J145
References
GL-89-01, GL-89-1, NUDOCS 9509210349
Download: ML20092J133 (37)

Text

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- NUCLEAR REGULATORY COMMISSION _

i UNITED STATES h"

G wassinoTow, o.c. sonss-oooi

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j THE CLEVELAls ELECTRIC ILLUMINATING COMPANY. ET AL.

I' DOCKET NO 50-440 i

l PERRY NUCLEAR POWER PLANT. UNIT NO. 1 i

AMENDMENT TO FACILITY OPERATING LICENSE l

Amendment No. 72 i

License No. NPF-58 3

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio

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Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated April 3, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I;

8.

The facility will operate in conformity with the application, the provisions of the'Act, and the rules and regulations of the Commission; 1

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 I

in compliance with the Commission's regulations; 4

D.

The issuance of this amendment will not be inimical to the common l'

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

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

I 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby amended to read as follows:

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9509210349 950915 ""

i PDR ADOCK 05000440 P

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. (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 72 are hereby incorporated into this license.

The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

'.v.

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s Jon B. Hopkins, Sentor Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

September 15, 1995 I

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ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACillTY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 i

Replace the following pages of the Appendix "A" Technical Specifications with p

the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Remove Insert 11 ii iii iii ix ix x

x xvi xvi xvii xix xix xxiii xxiii xxvii xxvii 1-5 1-5

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l-8 1-8 l-9 l-9 3/4 3-83 3/4 3-83 3/4 3-84

'3/4 3-85 3/4 3-86 3/4 3-87 3/4 3-88 3/4 3-89 3/4 3-89 3/4 3-90 3/4 3-90

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3/4 3-91 3/4 3-92 3/4 3-93 3/4 3-94 3/4 3-95 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-3 3/4 11-4 i

3/4 11-5 3/4 11-6 l

3/4 11-7 3/4 11-7 3/4 11-8 3/4 11-9 3/4 11 --

3/4 11-11 3/4 11-12 3/4 11-13 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 72 (Continued) i Eemove Insert 3/4 11-14 3/4 11-15 3/4 11-16 3/4 11-16 3/4 11-17 3/4 11-17

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3/4 11-18

-3/4 11-19 3/4 11-20 3/4-12 3/4 12-1 3/4'12-2 3/4 12-3 3/4 12-4 3/4 12-5 3/4 12-6 3/4 12-7 3/4 12-8

- 1 3/4 12-9 3/4 12-10 i

3/4 12-11 3/4 12-12 3/4 12-13 3/4 12-14 B 3/4 3-6 B 3/4 3-6 8 3/4.11-1 B 3/4 11-1 8 3/4 11-2 B 3/4 11-2 8 3/4 11-3 8 3/4 11-4 B 3/4 11-5 B 3/4 11-5 8 3/4 11-6 B 3/4 12 B 3/4 12-1 8 3/4 12-2 5-1 5-1 6-17 6-17 6-17a 6-17b 6-18 6-18 6-19 6-19 6-20 6-21 6-21 6-23 6-23 6-24 6-24 1

6-25 6-25 6 l

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DEFINITIONS SECTION DEFINITIONS -(Continued)

REE 1.24 Deleted 1.25 LOGIC SYSTEM FUNCTIONAL TEST.........................................

1-5

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3 1.26 MEMBER (S) OF.THE PUBLIC..............................................

1-5 1.27 MINIMUM CRITICAL POWER RATI0.........................................

.1-5 1.28 0FFSITE DOSE CALCULATION MANUAL......................................

1-5 1.29 OPERABLE - OPERABILITY...............................................

1-6 1.30 OPERATIONAL CONDITION - C0NDITION....................................

1-6 1.31 PHYSICS TESTS........................................................

1-6 1.32 PRESSURE BOUNDARY LEAKAGE............................................

1-6 1.33 PRIMARY CONTAINMENT INTEGRITY........................................

1-6 1.34 PROCESS CONTROL PR0 GRAM..............................................

1-7 I

1.35 PURGE - PURGING......................................................

1-7 1.36RATEDTHERMALPdWER..................................................

1-7 1.37 REACTOR PROTECTION SYSTEM RESPONSE TIME..............................

1-7 2

1.38~ REPORTABLE EVENT.....................................................

1-7.

J 1.39 ROD DENSITY..........................................................

1-7 1.40 SECONDARY CONT AINMENT INTEGRITY......................................

1-7 l

1.41 SHUTDOWN MARGIN......................................................

1-8 1.42 SITE B0VNDARY........................................................

1-8 i

1.43 Deleted 1

1.44 Deleted

1. 45 STAGGERED TEST BASIS.................................................

1-8 I'

1.46 THERMAL PDWER........................................................

1-9 i

l PERRY - UNIT 1 11 Amendment No. 72 1

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-DEFINITIONS SECTION-DEFINITIONS'(Continued)

PAGE' 4

1.47 TURBINE BYPASS SYSTEM RESPONSE TIME...............................

1-9 i

1.48 UNIDENTIFIED LEAKAGE..............................................

1-9

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1.49 UNRESTRICTED AREA.................................................

1-9 1.50 Deleted 1

1.51 VENTING...........................................................

1-9 Table 1.1, Surveillance Frequency Notation.............................

1-10 Tabl e 1.2, Operati onal Condi ti ons......................................

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PERRY - UNIT 1 111 Amendment No. 72 I

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE INSTRUMENTATION (Continued)

Meteorological Monitoring Instrumentation.............. 3/43-70.

Table 3.3.7.3-1 Meteorological Monitoring Instrumentation....................

3/43-71 k

Table 4.3.7.3-1 Meteorological Monitoring Instrumentation Surveillance Requirements.......................

3/43-72 j

Remote Shutdown System Instrumentation and Controls.... 3/43-73 Table 3.3.7.4-1 Remote Shutdown System

'7 Instrumentation and Controls.......

3/43-74 Table 4.3.7.4-1 Remote Shutdown System i

l Instrumentation Surveillance Requirements.......................

3/43-76 Accident Moni toring Instrumentation.................... 3/43-77 r!

Table 3.3.7.5-I Accident Monitoring Instrumentation....................

3/43-78 Table 4.3.7.5-1 Accident Monitoring Instrumentation Surveillance Requirements.......................

3/43-80 Source Range Monitors..................................

3/43-81 Traversing In-Core Probe System........................

3/43-82 Loose-Part Detection System............................

3/43-83 i

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PERRY - UNIT 1 ix Amendnent No. 72 l

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAQ1 INSTRUMENTATION (Continued)

Main Condenser Offgas Treatment System Explosive Gas Moni tori ng Instrumentation............................

3/43-89 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM...................

3/43-96 3/4.3.9 PLANT SY3 TEM ACTUATION INSTRUMENTATION................

3/43-98 Table 3.3.9-1 Plant Systems Actuation Instrumentation...................

3/43-100 Table 3.3.9-2 Plant Systems Actuation Instrumentation Setpoints.........

3/43-101 l

Table 4.3.9.1-1 Plant Systems Actuation Instrumentation Surveillance Requirements......................

3/43-102 3/4.4 REACTOR COOLANT SYSTEM n

3/4.4.1 RECIRCULATION SYSTEM Reci rc ul ati on Loops...................................

3/44-1 1

Figure 3.4.1.1-1 Thermal Power versus Core Flow....

3/44-3 Jet Pumps.............................................

3/44-4

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Recirculation Loop Flow...............................

3/44-5 Idl e Reci rcul ati on Loop Startup.......................

3/44-6 3/4.4.2 SAFETY /RELIEFVALVES Safety /ReliefValves..................................

3/44-7 p

Safety /ReliefValvesLow-LowSetFunction.............

3/44-8

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l PERRY - UNIT 1 x

Amendment No. 72 s

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LIMITING CONDITIONS FOR OPERATION AND' SURVEILLANCE RE0VIREMENTS SECTION PAG {

3/4.10 ' SPECIAL TEST EXCEPTIONS l

3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.......................... 3, i

3/4.10.2 R00 PATTERN CONTROL SYSTEM............................. 3 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.........................

3/410-3

'I 3/4.10.4 RE C I R CLM. AT I ON L00PS...................................i l

3/4.10.5 TRAINING STARTUPS.............................

3/410-5 3/4.11 RADI0 ACTIVE EFFLUENTS e

3/4.11.1 LIQUID EFFLUENTS i

Li q ui d Hol dup Tanks.................................... 3/411-7 t

'3/4.11.2 GASEOUS EFFLUENTS p9 Explosive Gas Mixture..................................

3/411-16 Ma i n C o n d e n s e r......................................... 3/411-17f 4

PERRY - UNIT 1 xvi(nextpageisxviii)

Amendment No. 72 f

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BASES-SECTION PAGE i

INSTRUMENTATION (Continued) 3/4.3.7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....................

B3/43-4a Seismi c Moni tori ng Instrumentation...................... B3/43-4b Meteorological Moni toring Instrumentation............... B3/43-4b Remote Shutdown System Instrumentation a nd Co n t ro l s............................................ B3/43-5 t

Accident Moni toring Instrumentation..................... B3/43-5 6

Source Range Monitors...................................

B3/43-5 Traversi ng In-Core Probe System.........................

B3/43-5 Loose-Part Detection System.............................

B3/43-6 I

Main Condenser Offgas Treatment System Explosive Gas Monitoring Instrumentation................

B3/43-6 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM.....................

B3/43-6 3/4.3.9 PLANT _SYSTENoS ACTUATION INSTRUMENTATION.................

B3/43-6 i

Bases Figure B 3 Water Level...../4 3-1 Reactor Vessel B3/43-8 3 /4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM....................................

B3/44-1 3/4.4.2 SAFETY /RELIEFVALVES....................................

B3/44-2 3/4.4.3-REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems...............................

B3/44-3 Operational Leakage.....................................

B3/44-3a 1

3/4.4.4 CHEMISTRY...............................................

B3/44-4 i

PERRY - UNIT'1 xix Amendment No.-67;72

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~ BASES SECTLQN PAGE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Liquid Holdup Tanks...................................

B3/411-2 3/4.11.2 GASEOUS EFFLUENTS Expl osi ve Gas Mi xture.................................

B 3/4 11-5 Main Condenser........................................

B3/411-5 4

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/9 PERRY - UNIT 1 xxiii Amendment No. 72 l

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ADMINISTRATIVE CONTROLS SECTION PAGE-6.12' HIGH RADIATION AREA........................................

6-23 6.13 PROCESS CONTROL PROGRAM (PCP)............................. 6-24 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM).....................

6-25 i

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' PERRY - UNIT 1 xxvii Amendment No.72 i

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DEFINITIONS i

LIMITING CONTROL ROD PATTERN

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1.22 A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e.,_ operating on a limiting value for APLHGR, LHGR,'or M PR.

LINEAR HEAT GENERATION RATE 1.23 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit i

length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

1.24 DELETED-LOGIC SYSTEM FUNCTIONAL TEST i

1.25'A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc. of a logic circuit, from sensor through and including the actuated j

device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be I

f performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MEMBER (S) 0F THE PUBLIC 1.26 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. _ This category does include persons who use portions of the site 4

for recreational, occupational, or other purposes not associated with the plant.

MINIMUM CRITICAL POWER RATIO 1.27 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists'in the core.

OFFSITE DOSE CALCULATION MANUAL (ODCM) j 1.28 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alann/ trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Specification 6.8.4 and (2) descriptions of the information that'should be included in the Annual Radiological Envircnmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7.

j PERRY - UNIT 1 1-5 Amendment No. 72 1

DEFINITIONS 1.

Capable of being closed by an OPERABLE containment automatic isolation system, or 2.

Closed by at least one manual valve, blind flange, or deactivated automatic valve, as applicable secured in its closed position.

b.

The containment equipment hatch is closed and sealed and the shield blocks are installed adjacent to the Shield Building, The door in each access to the annulus is closed, except for c.

normal entry and exit.

d.

The sealing mechanism associated with each Shield Building penetration, e.g., welds, bellows, or 0-rings, is OPERABLE.

The pressure within the secondary containment is less than or equal e.

to the value required by Specification 4.6.6.1.a. except for normal entry and exit to the annulus.

f.

The Annulus Exhaust Gas Treatment System is in compliance with the requirements of Specification 3.6.6.2.

SHUTDOWN MARGIN 1.41 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming all control rods are fully inserted except for the single control rod of highest reactivity worth which is assumed to be fully withdrawn and the reactor is in the shutdown condition; I

cold, i.e 68 F; and xenon free.

SITE BOUNDARY 1.42 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

1.43 DELETED 1.44 DELETED STAGGERED TEST BASIS 1.45 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains or other i

designated components obtained by dividing the specified test interval into n equal subintervals.

PERRY - UNIT 1 1-8 Amendment No. 72

DEFINITIONS b.

The testing of one system, subsystem, train or other designated.

component at the beginning of each subinterval.

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THERMAL POWER 1.46 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM RESPONSE TIME 1.47 The TURBINE BYPASS SYSTEM RESPONSE TIME consists of two separate time intervals: a) time from initial movement of the main turbine stop valve or control valve until 80% of turbine bypass capacity is established, and b) the time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve. Either response time may be measured by any series of sequential, overlapping, or total steps such that the entire response time is measured.

UNIDENTIFIED LEAKAGE 1.48 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.

UNRESTRICTED AREA

/ I 1.49 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of MEMBERS OF THE PUBLIC from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, conmercial, institutional, and/or recreational purposes.

1.50 DELETED VENTING 1.51 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

PERRY - UNIT 1 1-9 Amendment No. 72

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INSTRUMENTATIQN i

LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.8 The loose-part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS I and 2.

ACTION:

i With one or more loose-part detection system channels inoperable for a.

more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

l, b.

The provisions of Specification 3.0.3 are not applicable.

I SURVEILLANCE REQUIREMENTS 1

4.3.7.8 Each channel bf the loose-part detection system shall be demonstrated OPERABLE by performance of a:

a.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at least once per 18 months.

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PERRY

. UNIT 1 3/43-83(nextpageis3/43-89)

Amendment No. -}&r 72 I

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INSTRUMENTATION I

MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1

3.3.7.10 At least one main condenser offgas treatment system explosive gas monitoring instrumentation channel (IN64-N012 A/B) shall be OPERABLE with its alarm /tripsetpointsettoensurethatthelimitsofSpecification3.11.2are not exceeded.

APPLICABILITY: Whenever the main condenser offgas treatment system is in operation.

ACTION:

a.

With an explosive gas monitoring instrumentation channel alarm / trip setpoint less conservative than required by Specification 3.11.2, declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than one main condenser offgas treatment system explosive gas monitoring instrumentation channel OPERABLE, operation of the l

main condenser offgas treatment system may continue provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

If the recombiner temperature remains J

constant and' THERMAL POWER has not changed, the grab sample collection frequency may be changed to at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner.

c.

The provisions of Specification 3.0.3 are not applicable.

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SURVEILLANCE REOUIREMENTS i

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4 4.3.7.10 The explosive gas monitoring instrumentation channel (s) shall be demonstrated OPERABLE by perfonnance of a:

a.

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

b.

CHANNEL CALIBRATION at least once per 92 days. The CHANNEL CALIBRATION shall include the use of standard samples containing a nominal:

P 1.

One volume percent hydrogen, balance nitrogen, and 2.

Four volume percent hydrogen, balance nitrogen.

c.

CHANNEL FUNCTIONAL TEST at least once per 31 days.

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PERRY - UNIT I 3/4 11-1 (next page is 3/4 11-7) Amendment No. 72 l

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3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIOUID EFFLUENTS

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LIOUID HOLDUP TANKS i

. LIMITING CONDITION FOR OPERATION 3.11.1.4 The. quantity of radioactive material contained in any outside temporary tank, not including liners for shipping.radwaste, shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above specified tanks exceeding the above limit, insnediately suspend all additions of radioactive material to the tanks and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> i

reduce the tank contents to within the limit, and describe the events leading to the condition in the next Annual Radioactive i

Effluent Release Report pursuant to Specification 6.9.1.7.

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b.

The provis'i'ons of Specification 3.0.3 are not. applicable.

SURVEILLANCE REQUIREMENTS i

4.11.1.4 The quantity of radioactive material contained in each of the above specified tanks shall be detennined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

PERRY - UNIT 1 3/411-7 (next page is 3/411-16) Amendment No.-30, in, 72

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RADICACTIVE' EFFLUENTS 3/4.11'.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTUR[

LIMITING CONDITION FOR OPERATION i

3.11.2.6 The concentration of hydrogen in the offgas treatment system shall be limited to less than or equal to 4% by volume.

APPLICABILITY: Whenever the offgas treatnent system is in operation.

ACTION:

4 a.

With the concentration of hydrogen in the offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b.

With the continuous monitor inoperable, take the action specified in Specification 3.3.7.10, ACTION b.

l c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMthTS l

i 4.11.2.6 The concentration of hydrogen in the offgas treatment system shall I

be' determined to be within the above limits by continuously nonitoring the i

waste gas in the offgas treatnent system whenever the main condenser evacuation system is in operation with the hydrogen monitor OPERABLE as i

required by Specification 3.3.7.10.

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PERRY - UNIT 1 3/411-16 Anendment No. 4Wh 72

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INSTRUMENTATION s

BASES'

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JMONITORING INSTRUMENTATION (Continued)

I'00SE-PART DETECTION SYSTEM' 3/4.3.7.8 L

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-The OPERABILITY of.the loose-part detection system ensures that.

Esufficient. capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The

. allowable'out-of-service' times and surveillance requirements are. consistent m

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- with' the recommendations of. Regulatory Guide '1.133, " Loose Part Detection

- Program for-the. Primary System of Light-Water-Cooled Reactors," May.1981.

3/4.3.7.9 = DELETED.

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.3/4.3.7.10 MAIN' CONDENSER OFFGAS'TREATHENT SYSTEM EXPLOSIVE GAS MONITORING

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. INSTRUMENTATION.

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The main condenser offgas treatment system explosive gas monitoring instrumentation is provided to monitor the concentrations of potentially-explosive gas mixtures in the GASEOUS RADWASTE TREATMENT. SYSTEM to ensure the concentration is maintained below the flamability limits' of hydrogen. The OPERABILITY and use c6f this instrumentation to maintain the concentration of hydrogen'below its fla,mability limit provides assurance that releases of t

radioactive material will be controlled in confonnance with' the requirements L

of. General Design Criterion 60 and 63 of-Appendix A to 10 CFR Part 50.

e 3/4.3.8' TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed l:

-protection system instrumentation and'the turbine speed control valves are l

OPERABLE and will protect the turbine from excessive overspeed.

Protection

from' turbine excessive'overspeed is required since excessive'overspeed of the L

turbine could generate potentially damaging missiles which could impact and L

' damage safety related components, equipment or structures.

~3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION LThef plant systems actuation instrumentation is provided to initiate action

'of the containment spray system in the event of a LOCA with high containment i:

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l3 PERRY l-UNIT 1*

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PERRY - UNIT 1 B3/411-1 Amendment No. 72 J

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3/4.11 :RADI0 ACTIVE EFFLVENTS i

BASES' i

3/4.11.1.4 L10VID HOLDUP TANK 1 i

The. tanks listed in this specification include all those outdoor tanks containing radioactive material that are not surrounded by liners, dikes, or walls capable of holding the contents and that do not have overflows and

. surrounding area drains connected to the liquid radwaste treatment system.

Restricting the quantity of radioactive material contained in the specified c

tanks provides assurance that in the event of an uncontrolled release of the.

tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20. Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

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1 PERRY - UNIT'1 B3/411-2(nextpageisB3/411-5) Amendment No.72 1

RADI0 ACTIVE EFFLUENTS BASES j

3/4.11.2.6 EXPLOSIVE GAS MIXTURE

. This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the offgas holdup system is maintained below the flammability limits of hydrogen. Maintaining the concentration of hydrogen below its flammability limit provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

3/4.11.2.7 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to a MEMBER OF THE PUBLIC at and beyond the SITE B0UNDARY will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

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PERRY - UNIT 1 B3/411-5 Amendment No. 72 l

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e BASESSECTION3/4.12HASBEENDELETED

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i PERRY - UNIT 1 B3/412-1 Amendment No.72

5.0 DESIGN FEATURES 5.1 SITE EXCLUSION AREA. UNRESTRICTED AREA FOR LIOUID EFFLUENTS. AND SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.1 Figure 5.1.1-1 shows the PNPP site area, including the meteorological tower. The exclusion area boundary is 2900 feet from the center line of the reactor. All land within the exclusion. area is jointly owned by the CAPCO -

Group Companies. CEI controls the exclusion area; controls include mineral rights for oil, gas, and salt. In addition, the U.S. Coast Guard provides control over the Lake Erie portion of the exclusion area. A railroad spur serves the plant, heading in an east-north easterly direction from the railroad company right-of-way to the plant site. CEI owns the tracks and only

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railroad cars consigned to the PNPP are brought onto the site over this spur.

i Figure 5.1.1-1 also shows the liquid and gaseous effluent discharge locations as well as the plant SITE BOUNDARY for gaseous releases and the UNRESTRICTED AREA for liquid effluent releases.

LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1.

to 5.2 CONTAINMENT CONFIGURATION 5.2.1 The primary containment is a steel structure composed of a vertical right cylinder and ellipsoidal dome.

Inside and at the bottom of the primary containment is a reinforced concrete drywell composed of a vertical right cylinder and a steel head which contains an approximately 18'3" deep water filled suppression pool connected to the drywell through a series of horizontal vents. The primary containment has a minimum net free air volume of 1,160,000 cubic feet. The drywell has a minimum net free air volume of I

276,500 cubic feet.

DESIGN TEMPERATURE AND PRESSURE 5.2.2 The containment and drywell are designed and shall be maintained for:

a.

Maximum internal pressure:

1.

Drywell 30 psig.

2.

Containment 15 psig.

PERRY - UNIT 1 5-1 Amendment No. 72

ADMINISTRATIVE CONTR0lS 6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS (Continued) b.

In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equipnent.

c.

Post-accident Samplino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant i

gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

d.

Radioactive Effluent Controls Procram A program shall be provided conforming with 10 CFR 50.36a for the control of r,adioactive 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 i

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 set-point determination in 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 II, Column 2,

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM.

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 I to 10 CFR Part 50, PERRY - UNIT 1 6-17 Amendment No. -22. 00,72 i

ADMINISTRATIVE CONTROLS 6.8 PROCEDURES / INSTRUCTIONS AND PROGRAMS (Continued)

5) Detemination 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 i

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 comitment conforming to Appendix I to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at and beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20 Appendix B. Table II, Column 1, 8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas at and beyond the SITE B0UNDARY confoming to Appendix I to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC f 6m iodine-131, iodine-133, tritium, and all radionuclides in particulate fom with half-lives greater than 8 days in gaseous effluents released from each unit to areas at and beyond the SITE BOUNDARY confoming to Appendix I to 10 CFR Part 50, I

10)

Limitations on the annual dose or dose comitment to any MEMBER OF

't THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

e.

Radioloaical Environmental Monitorina Proaram 1

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 environmental exposure pathways.

The program shall (1) be contained in the ODCM, (2) confom to the l

guidance of Appendix I to 10 CFR Part 50, and (3) include the following:

i PERRY - UNIT 1 6-17a Amendment No.72 i

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ADMINISTRATIVE CONTROLS

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6.8 PROCEDURES / INSTRUCTIONS AND PR0GRANS (Continued)

1) Nonitoring, sampling, analysis, and reporting of radiation and i

radionuclides in the environment in accordance with the methodology j

and parameters in the ODCN,

2) A Land Use Census to ensure that changes in the use of areas at and 1

beyond the SITE B0UNDARY are identified and that modifications to the monitoring program are made if required by the results of this j

census, and

3) participation in an Interlaboratory Comparison program to ensure 3

that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample l

matrices are performed as part of the quality assurance program for environmental monitoring.

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6.9 REPORTING REQUIREMENTS 1

j ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code j

of Federal Regulations, the following reports shall be submitted to the i

Nuclear Regulatory Commission pursuant to 10 CFR 50.4 unless otherwise noted.

)

l STARTUP REPORT i

6.9.1.1 A sumary report of plant startup and power escalation testing shall l

be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

6.9.1.2 The startup report shall address each of the tests identified in the Final Safety Analysis Report Subsection 14.2.12.2 and shall include a descrip-l tion of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to I

obtain satisfactory operation shall also be described. Any additional specific l

details required in license conditions based on other commitments shall be included in this report.

6.g.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial a

i criticality, whichever is earliest.

If the startup report does not cover all j

three events, i.e., initial criticality, completion of startup test program, j

and resumption or commencement of comercial operation supplementary reports i

shall be submitted at least every 3 months until all three events have been completed.

PERRY - UNIT 1 6-17b Amendment No. 46,72 1

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l ADMINISTRATIVE CONTROLS j

ANNUAL REPORTS

• I 6.9.1.4 Annual reports covering the activities of the unit as described below j

for the previous calendar year shall be submitted prior to March 1 of each year. The initial report shall be submitted prior to March I of the year j

following initial criticality.

I 6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility, j

and other personnel, including contractors, receiving exposures greater than 100 mram/yr and their associated man-res exposure according to work and job functions ** e.g., reactor operations and 2

surveillance, inservice inspection, routine maintenance, special i

maintenance Ldescribe maintenance), waste processing, and refueling.

i The dose ass gnments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or j

film badge measurements. Small exposures totalling less than 20% of 4

the individual total dose need not be accounted for.

In the j

aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work l

functions; and b.

Documentation of all challenges to safety / relief valves.

I c.

Annual reports shall also include the results of specific activity i

analysis in which the primary coolant exceeded the limits of Speci fication,3,4.5. The following information shall be included:

4 (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first j

sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of l

one analysis after the radiciodine activity was reduced to less than limit. Each result should include date and time of sampling and the l

radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other l

radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the stehdy-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

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• A single submittal may be made for a multiple unit station. The submittal j

should combine those sections that are comon to all units at the station.

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• • This tabulation supplements the requirements of $20.407 of 10 CFR part 20.

PERRY - t241T 1 6-18 Amendment No. 72 i

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1 ADMINISTRATIVE CONTROLS 4

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AfSIUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating 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 summaries, interpretations, and analysis of trends of the results of the Radiological Environmentaf Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the 00CM and 4

(2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

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j A3000AL RADICACTIVE EFFLUENT RELEASE REPORT i

6.9.1.7 The Annual Radioactive Effluent Release Report covering the l

operation of the unit during the previous calendar year shall be submitted i

annually. The report must be submitted as specified in 10 CFR 50.4, and the i

time between submission of reports must be no longer than 12 months. The i

report shall include a summary of the quantities of radioactive liquid and gaseous efficents and solid waste released from the unit. The material i

i provided shall be (1) consistent with the objectives outlined in the ODCN and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

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i PERRY - UNIT 1 6-19 (next page is 6-21)

Amendment No.-48, 72 i

4 ADMINISTRATIVE CONTROLS i

1 MONTHLY-OPERATING REP 0RTS 6.9.1.8 Routine reports of operating statistics and shutdown experience shall be submitted to the Nuclear Regulatory Consnission pursuant to 10 CFR 50.4 on a monthly basis, with a copy to the Director, Office of Resource 4

Management, U. S. Nuclear Regulatory Comission, Washington, D.C. 20555, no later than the 15th of each month following the calendar month covered by the j

- report.

CORE OPERATING LIMITS REPORT i

6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following-(1) The Average Planar Linear Heat Generation Rate (APLHGR) for Technical Specification 3.2.1.

(2) The Minimum Critical Power Ratio (MCPR) for Technical Specification 3.2.2.

[

(3) The Linear Heat Generation Rate (LHGR) for Technical Specificati,o,n 3.2.3.

1 (4) The Simulated Thermal Power Time Constant for Technical Specification 3.3.1.

The analytical methods used to determine the core operating limits shall f

be those previously reviewed and approved by NRC in NEDE-24011-P-A, General i

Electric Standard Application for Reactor Fuel.

(The approved revision at the l

time reload analyses are performed shall be identified in the COLR.)

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thennal-hydraulic limits, i

ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and 4

accident analysis limits) of the safety analysis are met.

1 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be submitted upon issuance for each reload cycle, i

to the Nuclear' Regulatory Comission pursuant to 10 CFR 50.4.

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PERRY - UNIT 1 6-21 Amendment No. -33, S, S, 55, 72 l

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• ADMINISTRATIVE CONTROLS RECORDRETENTION(Continued) 1.

Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life coninences and associated installation and maintenance records.

m.

Records of analyses required by the radiological environmental moni-toring program that would pennit evaluation of the accuracy of the analysis at a later date. This would include procedures effective i

at the specified times and QA records showing that these procedures were followed, n.

Records of reviews perfonned for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 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.

6.12 HIGH RADIATION AREA r

6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2)of10CFRPart20,eachhighradiationareainwhich the intensity of radiation is greater than 100 mrem /hr** but less than 1000 mrem /hr shall be barr,icaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter j

4 such areas shall be provided with or accompanied by one or more of the following:

i a.

A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device

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may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.

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c.

A health physics qualified individual 1.e., qualified in accordance with ANSI N18.1-1971, with a radiation dose monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Plant Health Physicist.

• Health physics personnel or personnel escorted by health physics personnel

. shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high level radiatio' areas.

• • Meas ement made at 18 inches from source of radioactivity.

PERRY - UNIT 1 6-23 Amendment No. 72

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ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the i

body could receive in I hour a dose greater than 1000 mrem

• shall be provided with uniquely keyed locked doors or continuously guarded to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor or the Plant Health Physicist. Doors shall i

remain locked except during periods of access by personnel under an approved RWP. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour. a dose in excess of 1000 mrem

• that are located within large areas, such as the containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device.

6.12.3 In addition to the requirements of Specifications 6.12.1 and 6.12.2, for individual areas accessible to personnel such that a major portion of the body could receive in I hour a dose in excess of 3000 mrem *, entry shall require an approved RWP which will specify dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.

In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote, such as use of closed circuit TV cameras, may be made by personnel qualified in radiation protection procedures to provide positive exposure control over activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:

a.

Shall be documented and records of reviews perfonned shall be i

retained as required by Specification 6.10.3.n.

This docu-l mentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determination that the change will maintain the overall confonnance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, i

b.

Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.

• Measurement made at 18 inches from source of radioactivity.

PERRY - UNIT 1 6-24 Amendment No. 493 72

P ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 Changes to the ODCM:

a.

Shall be documented and records of reviews perfonned shall 'be retained as required by Specification 6.10.3.n.

This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)

A detennination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, the Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

l b.

Shall become effective after review and acceptance by the PORC and j

the approval of the Plant Manager.

c.

Shall be submitted to the Comission in the form of a complete.

legible copy of the entire 00CM 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 inqjcating(e.g. area of the page that was changed, and shall the indicate the date

, month / year)thechangewasimplemented.

PERRY - UNIT 1 6-25 Amendment No.-49, 72