ML20062B052

Amend 47 to License DPR-44,changing Tech Specs Re Instrumentation That Initiates or Controls Core & Containment Cooling Sys,Administrative Controls & safety-related Snubbers

ML20062B052
Person / Time
Site:	Peach Bottom
Issue date:	10/10/1978
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062B049	List: ML20062B046 ML20062B052 ML20062B055 ML20062B058 ML20062B061
References
NUDOCS 7810230016
Download: ML20062B052 (21)

Text

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[ e, UNITED STATES NUCt. EAR REGULATORY COMMisslON 3 )e WASHINGTON, D. C. F '

%, - ,j f PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-277

, PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 47 License Nc. OPR-44

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

A. The appitcations for amendment by Philadelphia Electric Company, et al (the licensee) dated May 26 and September 5, 1978, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; s B. The facility will operate in confonnity with the '

applications, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (1) 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 in compliance with the Comission's regulations; ,

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

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices

^ A and B, as revised through Amendment ?!o. 47, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION s L ----

Thomas , t Chief Operating Reactors Branch #3 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: October 10, 1978

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I ATTACHMENT TO LICENSE AMENDMENT NO. 47 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Revise Appendix A Technical Specifications as follows:

1 Remove Replace 111 iii 67 67 68* 68*

t 102a 102a i' 115* 115*

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127 127 177* 177*

178 178 249 249 250 250 253 253 254 254 254b 254b 257 257 262 262 263 deleted 264 deleted

• No changes on this page A b

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PBAPS l

TABLE OF CONTENTS (cont' d)

SURVEILLANCE LIMITING CONDITIONS FOR OPERATION .REQUIR EMENTS PAGE NO.

l 3.14 FIRE PROTECTION 4.14 240c  !

l A. Water Fire Protection System A 240c I B. CO2 Fire Protection System B 240g j C. Fire Detection C 2401 -

D. Fire Barrier Penetrations n 240j 5.0 MMOR DESIGN FEATURES 241

. 6.0 ADMINISTRATIVE CONTROIS 243 6.1 Responsibility 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246 6.4 Training 246 6.5 Review and Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit Violation 253 6.8 Procedures 253 6.9 Reporting Requirenents 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 ?lre Irptection Inspections 261 6.13 Bigh Radiation Area 262 l Amendment No. 29, 47 -lii-

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Unit 2 TABLE 3.2.5 (Cont ' d)

:s Unit 2

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INSTRUMENTATION TilAT INITIATES OR CONTROLS T!!E CORE AND CONTAINMENT l

COOLIHG SYSTEMS 4

I A Minimum No. '

j of Operable Number of Instru-Instrument Trip Function Trip Level Settiry ment Channels Pro- Remarks j ctwnnels Per vided by Design

IILL'_1x u=af11 _.

2 Core Sgray Pump 6* I sec 4 timers l In conjunction with loss

• Start Timer to 1 1 sec 4 timers of power initiates tte starting of CSCS gesps.

1 LPCI Ptanp Start 0<t< 1 sec 2 timers This specif1 cation shall be Timer 5 1 1 sec 2 timers ef fective until replacement o f t he " O < t < t sec" timers with auxiliary relays.

2 LPCI Ptanp Start 5 1 1 sec 4 timers This specification shall be Timer (Two pumps) effective after replacement 8 g a of the "O < t < 1 sec" timers g M with suxiliary relays. g

• en s 1 Auto Blowdown 90 <_t< 120 2 timers in conjunction with Timer Low peactor Water 14 vel, High Drywell Pressure i and LPCI or Core Spray l Pump running interlock, t initiates Auto Blowdown. . l 2 HilR (LPCI) Pump 50 + 10 psig 4 channels po ters ADS actuation Discharge Pressure pending confirmation of Interlock

_i Low Pressure core cool-ing system operation.

2 Core spray Pump 1851 10 pelg 4 cha nnel s (LPCI or Core spray I Disclearge Pressure Pump renning interlock.) I Interlock I

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TABLE 3.2.B (Cont'd)

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l INSTRUMENTATION Tl!AT INITIATdS OR CONTROLS TIIE CORE AND CONTAI!!MLNT -

COOLING SYSTEMS ~

I Minimum No. _

of Operable Number of Instru-Instrument Trip Function Trip Level Setting ment Channels Pro- .

Chennels Per vi e y sign Remarks '

Trip System (l) 1 RilR (LPCI) Trip System bus power NA 2 Inst. Channels Monitors availability monitor of power to. logic ...

systems.

1 Core Spray Trip .

NA 2 Inst. Channels System bus power Monitors availability monitor of power to logic systems.

1 ADS Trip System bus 3 Inst. Channels NA

power monitor Monitors availability

! of power to logic i

systems.

a 1 'IIPCI Trip System bus NA 2 Inst. Channels

$: power monitor Monitors availability  ;

of power to logic systems.

' j 1 RCIC Trip System bus power monitor NA 2 Inst. Channels Monitors availability  !

of power to logic i systems.

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PBAPS thit 2 LIMITING CONDITIONS FOR OPERATION SURVEILINCE REQUIRDEEIS r

3.3.B Control Rods (Cont'd) 4.3.B Control Rods (Cont'd)

b. Whenever the reactor is in the b.1. Prior to the start of control rod startup or run modes belcw 25% withdrawal towards criticality rated power the Ibd Worth and prior to attaining 25% of Minimizer shall be operable or a rated power during rod insertion second licensed operator shall at shutdown, the Rod Worth Mini:nizer verify that the operator at the (RWM) shall be demonstrated to be reactor console is following operable by the following checks:

the control rod program. I

a. 'Ihe RWM couputer on line diagnostic test shall be successfully performed.

b. Prior to the start of control rod withdem al only, proper annunciation of the selection error of at least one out-of-sequence control rod in a fully inserted group shall be verified.

c. 'Ibe rod block function of the R E shall be verified by withdrawing the first rod during start-up only as an out-of-sequence control rod no more than to the block point.

2. Following any loading of the rod 1 worth minimizer sequence program I into the computer, the i correctness of the control rod l withdrawal sequence input to the i ,

RWM conputer shall be verified. I

c. If Specifications 3.3.B.3a or b c. When required, the presence of the  !

cannot be met the reactor shall second licensed operator to verify

( not be started, or if the reactor the following of the correct rod is in the run or startup nodes program snall be verified and at less than 25t(*) rated power, recorded, it shall be brought tu a shutdown condition immediately.

• After installation of improved instrumentation authorized by Amendment No. 43, 214 power limit l applies.  ;

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l Amendment No. MM 47 -192a-

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• 1 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL 4.4 STANDBY LIQUID CONTROL SYSTEM SYSTEM Applicability: Applicability:

Applies to the operating Applies to the surveil- l status of the Standby lance requirements of

-Liquid Control System. , the Standby Liquid Con-trol System. (

I Objectiver Objective:

- To assure the avail'bility a To verify the operability I~) ^

of a system with the capa- - of the Standby Liquid bility to shut down the Control System.

reactor and maintain the l shutdown cordition without the use of control rods.

Specification: Specification:

A. Normal System Availability A. Normal System Availability

1. During periods when fuel is The operability of the in the reactor and prior to Standby Liquid Control startup from a Cold Condi- System the performance of tion, the Standby Liquid the following tests:

Control System shall be 1. At least once per month operable, except as speci- each pump loop shall be fied in 3.4.B below. This functionally tested by i system need not be operable

(- when the reactor is in the recirculating domineralized water to the test tank. l Cold Condition and all con-trol rods are fully insert- 2. At least once during each  ;

- ed and Specification 3.3. A operating cycle:

is met. (a) Check that the setting of I the system relief valves is ,

1400 < P < 1680 psig. l (b) Manually initiate the sys-

'em, except explosive

.lves. Pump boron solu-on through the recircu-

.ition path and back to the Standby Liq" M Control Solution Tank. Minimum pump flow rate of 39 gym against a system head of 1225 psig shall be veri-fled. After pumping boren solution the system will be flushed with demineral-ized water.

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i PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILIR;CE REQUIREMEICS 3.4 STANDBY LIOUID CONTROL 4.4 STANDBY LIQUID CO!7PROL SYSTEM (Cont 'd) SYSTEM (Cont'd)

(c) Manually initiate one of

, the Standby Liquid Control control System Pumps and pump demineralized water into the reactor vessel from the test tank.

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This test checks explosion of the charge associated

with the tested loop, (3 ~

proper operation of the l explosive valves, and pump l

, operability. The replacement charges to be installed will be selected from the same manufactured batch as the tested charge.

(d) Both systems, including both explosive valves, shall be tested in the course of two operating cycles.

B. Operation with Inocerable B. Surveillance with Components Inocerable Components L,

1. From and after the date that 1. When a component is found to a redundant component is made be inoperable, its redundant or found to be inoperable, component shall be demonstrated specification 3.4.A.1 shall be to be operable immediately and considered fulfilled and daily therafter until the continued operation permitted inoperable component is provided that the component is repaired.

returned to an operable condition within seven days.

Amendment No. 47 4

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'l LIMITING CONDITIONS FOR OPERATION SURVEILIRCE RBDUIREMENIS 3.5.A core Soray and LPCI 4.5.A Core Soray and LKI Subsystem (cont'd) Suosystem (cont'd)

Euth CSS shall be operable whenever Item Frecuenev irradiated fuel is in the vessel and prior to reactor startup from a (d) Pu=p Flow Fate Once/3 months Cold Shutdown condition except as specified in 3.5.A.2 and 3.5.F.3 Both loops shall deliver at least below: 6250 gpm against a system head corresponding to a reactor vessel pressure of 105 psig.

(e) Core Spray Header AP Instrumentation Check Once/ day Calibrate Once/3 months (f) Operability check In accordance to ensure that with 4.5.A.2, pumps will start 4.5.A.4 and and notor operated 4.5.A.5 l injection valves will open.

2. From and after the date that one of 2. When it is determined that one the core spray subsystems is made core spray subsystem is inoperable, or found to be inoperable for any the operable core spray subsystem reason, continued reactor operation and the LKI subsysteres shall be is permissible only during the demonstrated to be operable in

( succeeding seven days provided that accordance with 4.5.A.l(F) and during such seven days all active 4.5.A.3 (e) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at components of the other core spray least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter subsystem and active components of until the inoperable core spray the IJCI subsystems are operable. subsystem is restored to operable status.

3. LPCI Subsystem Testing shall '

be as follows:

Item Frecuencv (a) Sinulated Automatic Once/ operating Actuation Test Cycle (b) Pump operability Once/l month

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Amendment No.[ 47 -125-

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i PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILINCE REQUIRINEN'IS 3.5.A Core Spray and LPCI  !'

4.5.A Core Spray and LPCI Subsystem (cont'd) Subsystem (cont'd)

3. ho independent Low Pressure Coulant Item Frecuency Injection (LPCI) subsystems will be

, operable with each subsystem (c) Motor Operated Once/ month comprised of: valve operacility

a. (ho 33-1/31) capacity peps, (d) Pung Flow Rate Once/3 months

, b. An operable flow path capable of Each LPCI pep shall deliver 19,999 l taking suction from the gpn against a system head correspon-suppression pool and transferring ding to a vessel pressure of 29 psig the water to the reactor pressure based on individual pmp tests.

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vessel, and

c. During power operation the LKI (e) Operability check In accordance system cross-tie valve closed to ensure that with 4.5.A.2, and the associated valve motor pumps will start 4.5.A.4 and i operator circuit breaker locked and motor operated 4.5.A.5 i in the off position. injection valves will open Both LPCI subsystems shall be operable whenever irradiated fuel is in the reactor vessel, and prior to reactor startup from the Cold Shutdown Condition,.

except as specified in 3.5.A.4 and 3.5.A.5 below.

4. From and after the date that one of 4. When it is determined that one of

( the four LKI pumps is made or the RHR (LPCI) pumps is inoperable found to be inoperable for any at a time when it is required to reason, continued reactor operation be operable, the remaining LPCI is permissible-only during the pumps and associated flow paths i

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succeeding-seven days provided that and both core spray subsystenrs shall '

during such seven days the remaining be demonstrated to be operable in I active cocponents of the LPCI accordance with 4.5.1(f) and  !

subsystems, and all active conponents of both core spray 4.5.A.3(e) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at  !

least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter  !

subsystems are operable. until the L KI subsystem is restored j to operable status. t i

5. From and after the date that one 5. When it is determined that one of LKI subsystem is made or found the LPCI subsystc.m is inoperable i

i to be inoperable for any reason, both core spray subsystems and the continued reactor operation is renaining LKI subsystem shall be permissible only during the demonstrated to be operable within succeeding 7 days unless it is sooner 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at least once for 72 i made operable, provided that during hours thereafter until t.5 f.KI  !

such 7 days all active components of subsystem is restored to operab'e both core spray subsystems and the status.

remaining LKI subsystem are operable.

Amendment No. )( 47 -126-

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f PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILIRCE REUJIREMENTS 3.5.A Core Soray and LPCI 4.5. A Core Soray and IJCI Subsystem (cont'd) Subsystem (cont'd)

6. All recirculation pump discharge 6. All recirculation p. " discharge valves shall be operable prior to valves shall be testeu for i reactor startup (or closed if operabilty during any period permitted elsewhere in these of reactor cold shutdown exceeding specifications). 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been performed during the preceeding 31 days.

7. If the requirements of 3.5.A cannot

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be met, an orderly shutdown of the

( reactor shall be initiated and the reactor shall be in the Cold Shutdown Condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

B. Containment Cooling B. Containment Coolins Subsystem (HPSW) Subsystem (HPSW)

1. Except as specified in 3.5.B.2, 1. Containment Cooling Subsystem 3.5.B.3, 3.5.B.4, and 3.5.F.3 'Ibsting shall be as follows:

below, all containment cooling subsystem loops shall be operable Item Frequency whenever irradiated fuel is in the reactor vessel and reactor coolant (a) Pump Once/nonth [

temperature is greater than 212*F, Operability and prior to reactor startup frcra a Cold Shutdown Condition. (b) Motor operated Once/::enth valve operability 6.

(c) Pump Capacity After pug Test. Each HPSW maintenance pump shall and every

' deliver 4500 3 months.

gpm at 280 psig.

(d) Air test on Chce/5 years drywell and torus headers and nozzles.

2. From and after the date that any two 2. When it is determined that any two HPSW pmps are made or found to be HPSW pumps are inoperable, the inoperable for any reason, continued renaining components of the reactor operation is permissible only containment cooling subsystems shall during the succeeding thirty days, be demonstrated to be operable unless such pmp is sooner made immdiately and weekly thereafter.

operable, provided that during such thirty days all active comonents of -

the containment cooling subsystem are operable.

Amendment No. M 47 .

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.D Primary Containment 4.7.D Primary Containment Isolation Valves Isolation Valves

1. During reactor power oper- 1. The primary containment ating conditions , all isola- isolation valves surveillance tion valves listed in Table shall be performed as follows :

3.7.1 and all instrument line flow check valves shall be a. At least once per operating operable except as specified cycle the operable isola-in 3.7.D.2. tion valves that are power

. operated and automatically initiated shall be tested for simulated automatic initiation and closure

, times.

b. At least once per quarters (1) All normally open power operated isolation valves (except for the I main steam line power-operated isolation valves) shall be fully closed and reopened.

l (2) With the reactor power less than 754 trip main steam isolation valves individually and verify

,. closure time.

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c. At least once per week the i

main steam line power-l operated isolation valves shall be exercised by par-tial closure and subsequent reopening.

d. At least once per operating  !

cycle the operability of l the reactor coolant system '

instrument line ficw check valves shall be verified.

2. In the event any isolation 2. Whenever an isolation valve valve specified in Table listed in Table 3.7.1 is incper-

3. 7.1 becomes inoperable , able, the position of at least reactor power operation may one other valve in each line continue provided at least having an inoperable valve shall one valvo in each line having be recorded daily.

an inoperable valvo shall be  :

in the mode corresponding to j the isolated condition. i

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PBAPS 5

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated. The reactor

_shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless Specification 3.7.D.1 or 3.7.D.2 can be met.

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c PBAPS 6.5.2 Cperation and safety Review Ccamittee Function 6.5.2.1 The Operation and Safety Review Committee shall function to provide independent review and audit of designated activities in the area of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radicchemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices (the members of the OSR Ccmmittee will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix E.

Additionally, they will be cognizant of the corporate Quality Assurance Program and will have

(]) the corporate Quality Assurance Organization available to them.)

Composition

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6.5.2.2 The operation and Safety Review Committee shall be .

ccaposed of the:

Manager-Electric Eroduction Department (Chairman)

Superintendent-Maintenance Division Superintendent-Services Division l l

Nanager-Engineering S Research Department (Vice Chairman) l Chief Mechanical Engineer  ;

Chief Electrical Engineer i Assistant Director-Research Division i

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Amendment No. [ 47 -249-

PBAPS Alternates 6.5.2.3 Alternate Members shall be appointed in writing by the OSR Committee Chairman. Each permanent member shall have a designated alternate to serve in his absence, and a current list of these alternates shall be maintained in Committee zecords. Each alternate member will serve on a continuing basis.

Consultants 6.5.2.4 Consultants shall be utilized as determined by the OSR Committee Chairman to provide expert advise to the OSR

, committee.

Neetina Frequency 6.5.2.5 The CSR Committee shall meet at least once per six l months.

l Quorum

6. 5. 2. 6 A quorum of the OSR Committee shall consist of the Chairman or Vice Chairman or their designated alternates and four members or their alternates. No more than a minority of the quorum shall have line j responsibility for operation of the f acility.

Review

6. 5. 2. 7 The CSR Committee shall review:

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a. The safety evaluations for 1) changes to procedures,-equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes tc procedures, equipment or systems which involve an unreviewed safety  ;

question as defined in 10 CFR 50.59. i

c. Proposed tests or experiments which involve an .

unreviewed safety question as defined in 10 CFR 50.59. '

i Amendment No. M 47 '

-250-

- _ _ m PEAPS 6.6 FeLortable Occurrence Action 6.6.1 The following actions shall be taken in the event of a Reportable occurrence:

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the PORC and submitted to the OSR Committee and the Superintendent, Generation Division-Nuclear.

.r) 6.7 Safety Limit violation 6.7.1 The following actions shall be taken in the event a Safety Limit is viclated:

a. The provisions of 10 CFR 50.36 (c) (1) (i) shall be complied with immediately,

b. The Safety Limit violaticn shall be reported to the commission, the Superintendent, Generation Division-Nuclear or, in his absence, the Superintendent, Generation Division--Eassil-Bydro and to the OSR Committee immediately.

c. A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PORC. This report

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shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon I

l, . facility ccmponents, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit violaticn Report shall be submitted to the Commission, the OSR Committee and the Superintendent, Generation Division-Nuclear within 14 days of the violaticn.

6.8 Procedures 6.8.1 Written procedures and administrative policies shall be '

established, isplemented and maintained that meet the '

requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USAEC Regulatory Guide 1.33 (November l l

1972) except as provided in 6.8.2 and 6.8.3 below. l  :

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Amendment No. 47 -253-

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PEAPS 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and l approved by the Station Superintendent or his designated j alt ernat : per Specificaticn 6.1.1 prior to implementation j and perirdically as set forth in administrative j procedures. l 6.8.3 Temporary changes to procedures of 6.8.1 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 plant management staff, at least one of whom holds a Senior f- Reactor Operator's License on the unit affected.

c. The change is documented, reviewed by the PORC and approved by the Station . Superintendent within 14 days of Laplementation.

6.9 Reportino Requirements In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following .

identified reports shall be submitted to the Director of the appropriate Regional Cffice of Inspection and Enforcement unless otherwise noted.

6.9.1 Rcutine Recorts

a. Startur Mecort. A summary report of plant startup and 4

( power escalation testing shall be submitted following

-(1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installaticn 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 hyraulic performance of the plant. The report shall address ,

each of the tests identified in the ESAR and shall in '

general include a description of the measured values l of the operating conditions or* characteristics  !

obtained during the test program and a comparisen of '

these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other conmitments shall be reported in this report.

Amendment No.I.M. 47 -254-t _ _

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l PBAPS 6.9.1 Continued

c. Monthly Operating Report Routine reports of operating statistics and shutdown experience, and a narrative summary of the operating experience shall be submitted on a monthly basis to i the Of fice of Management and Program Analysis (or its  ;

successor) , U.S. Nuclear Regulatory Commission,  ;

Washington, D.C. 20555, with a copy to the appropriate l

Regional Office, to be submitted no later than the

, 15th of the month following the calendar month covered by the report.

6.9.2 Reportable Occurrences Reportable occurrences, including corrective actions and

, measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of the occurrence. In case of ccrrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the orignal report date.

a. Prompt Notification With Written Followup. The types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the appropriate Region Office, or his designate no later i

C than the first working day following the event, with a written followup report within ten working days. The written followup report shall shall include, as a minimum, a completed copy of a licensee event report

. form. Information provided on the licensee event .

report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

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Amendment No. 27, 47 -254b-

g PBAPS 3

6.9.2 Continued (3) Cbserved inadequacies in the inplesentation of administrative or l procedural controls which threaten to cause reduction of degree of

, redundancy provided in reactor protection systems or engineered safety feature systems.

(4) Abnormal degradation of systems other than those specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.

i Note: Sealed sources or calibration sources are not included under this

item. Leakage of valve packing or gaskartr, within the limits for identified leakage set forth in technical specifications need not be reported under this item.

6.9.3 Unique Reporting Requirements Special reports shall be submitted to the Director of the appropriate Regional Office within the time period specified for eacit report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Ioss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of the event.

b. Reactor vessel inservice inspection, Specification 3.6.G and 4.6.G within 90 days of the completion of the reviews.

c. Secondary Containment leak rate testing, Specification 4.7.C within 90 i days of the cocpletion of the test. l s d. Primary containment leak rate testing, Specification 4.7.A within 90 1 days of the coupletion of the test. l

e. Release rate of Radioactive Effluents, Specification 3.8.B.7, 3.8.C.3.b,  ;

3.8.C.5.

I i

f. Sealed source leakage in excess of limits, Specification 3.13.3.

g. Effluent Releases Effluent data should be summarized monthly, except in instances when more data is needed, and the items listed below reported semi-annually

on the standard form " Report of Radioactive Effluents".

i (1) Gaseous Releases l l

! (a) Total radioactivity released (in curies) of noble and activation gases.

(b) maxiaum noble gas release rate during any one-hwr period.

Amendnent No. [, 47

-257-t

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PBAPS 6.13 High Radiation Area 6.13.1 In lieu of the " control device" or " alarm signal" required by 1.aragraph 20.203 (c) (2) of 10 CFR 20:

a. Each Eigh Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit. Any individual or l group of individuals permitted to enter such areas l shall be provided with or accompanied by one or more of the following: ,  ;

1. A radiation monitoring device which l i

continuously indicates the radiation dose rate l in the area.

{ l

2. A radiation acnitoring device which l continuously intergrates the radiation dose l 4

rate in the area and alarms when a preset '

integrated dose is received. Entry into such  ;

areas with this monitoring device may be made ,i after the dose rate levels in the area have been established and personnel have been made i

l l knowledgeable of them. j l

3. An individual qualified in radiation {

• {~} protection procedures who is equipped with a j ,

radiation dose rate monitoring device. This t i

' individual shall be responsible for providing , .

positive control over activities within the area and shall perform perdiodic radiation '

l surveillance at the frequency sr ified by the j  ;

plant Health Physicist or his de:,.gnee on the '

Radiation Work Permit. L

b. Each High Radiation Area in which the intensity of 7 radiation is greater than 1000 mrem /hr shall be subject to the provisiens of 6.13.1 (a) above. In j addition, locked doors shall be provided to prevent unautbo d .ad entry into such areas and the l l l

keys shall be maintained under the administrative l control of the Shift Superintendent or Shift l Supervisor.

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