ML18029A149

Proposed Tech Specs Reflecting New TVA Organization for Ofc of Nuclear Power

ML18029A149
Person / Time
Site:	Browns Ferry
Issue date:	09/27/1984
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18029A148	List: ML18029A147 ML18029A149
References
TAC-56027, TAC-56028, TAC-56029, TVA-BFNP-TS-201, NUDOCS 8410040371
Download: ML18029A149 (142)

Text

ENCLOSURE 1

PROPOSED TECHNICAL SPECIFICATION REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1., 2, AND 3 (TVA BFNP TS 201) 84i004037i 840927 PDR ADOCK 05000259 PDR

r

PROPOSED UNIT 1

TECHNICAL SPECIFICATION REVISIONS

0 d

'4 0

Section B.

Core Monitoring

~Pa e Ne.

305.

Spent Fuel Pool Water D.

Reactor Building Crane 306 307 E.

Spent Fuel Cask 307 F.

Spent Fuel Cask Handling-Refueling Floor e

3.11/4.11 Fire Protection Systems 308 315 A.

High Pressure Fire Protection System 315 B.

CO Fire Protection System C.

Fire Detectors D.

(Deleted)

~

~

~

~

~

~

~

~

E.

Fire Protection Systems Inspection F.

(Deleted)

~

~

~

. 319 320 322 322 G.

Air Masks and Cylinders 323 H.

Continuous Fire Watch 323 I.

Open Flames, Welding Cable Spreading Room and Burning in the 323 5.0 Ma)or Design Features 330 5.1 Site Features 330 5.2 Reactor 330 5.3 Reactor Vessel 330 5.4 Containment 330 6.0 5.5 Fuel Storage 5.6 Seismic Design Administrative Controls

~

~

~

~

330 331 332-6.1 Organization 332

J

Section

~Pa e.No.

6.2 Review and A'udit.

332'.3 Procedures 338 6.4 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation 346 6.5 Actions to be taken in the Event Limit is Exceeded 6.6 Stat'ion Operating Records a Safety-

~

~

~

=- '346

~

~

~

~

~

346 6.7 Reporting Requirements 349 6.8 Minimum Plant Staffing 358

I

~

a

~

LIST OF ILLuSTRATIONS Figure 2.1.1 2.1-2 Title

~Pa e No.

APRM Flow Reference Scram and APRM Rod Block Settings e

~

~

~

~

~

~

~

~

~

~

e

~

~

'e

~

~

~

e 13 APRM Flow Bias Scram Vs. Reactor Core Flow 26 4.1-1 Graphic Aid in the Selection of an Adequate Interval Between Tests 4.2-1 System Unavailability 49 1.1 9 3.4-1 Sodium Pentaborate Solution Volume Concentration Requirements 130 3.4-2 Sodium Pentaborate Solution Temperature Requirements..................

139 3.5.K-1 3.5.7 3.6-1 3.6-2 6:1-1 Offsite Organization for and Technical Support Facility Management

~

~

~

~

~

~

~

~

~

~

MCPR Limits.

Factor e

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

K Minimum Temperature

'F Above Change in Transient

. Temperature Change in Cha rpy V Trans ition-Temperature Vs.

Neutron Exposure 172b 173 194 195 I

I 361 6.1-2 G.?-1

~

'6:3-1 Facility Organization (Deleted)

(Delted)

I

~

~

~

~

~

~

~

~

~

~

362 364

~

~

~

~

~

~

~

e 363

LIHITZNG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS PROI'ECTION SYSTEMS

4. 11 FIRE PRC7PECTION SYSTEMS 2 ~

>e

>(I )h $

'r I,

~

'I JeN h

3.

0 5

6.

r*

fe

<' Ije>r'h' I

~ II

',~,

I,

'art

'lf>I If specification

3. 11.A. 1. a or 3 ~ 11 A..l. b cerrrnot be

met, a patrolling fire watch with portahl

~ fire equipment ave l.abl shall be establi..hed to insure that eac'n area where protection is lost is checked hourly.

If only one high pre s sure fire purrr p is

operable, the reactors may remain in operation for a period not to exceed 7 day

, provided the requir ments of speci fica hi on

3. 11.A. 1. b ahnve arc met.

If speci fication 3.11.A.3 cannot be met, the reactor shall be placed in the cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Removal of any component in the High Pressure Fire Syst m

from service for any reason other than testing or emergency operations shall require Plan t Manager approval.

The Raw Service Water storage tank level shall be maintained above level 723'7<r by the raw service water pullrps 31 2 e When it is determined that only one pump is

operable, that pump shall be demonstrated operable irnrnediately and daily thereafter until spr.ci fication 3.11.A.1.a can be met.

Itern Simulated automatic and manual actua tion of raw service water pumps and operatiorr of tank level s~itches

~reeuenc Once/yea 4 ~

5.

The high pressure fire protection system pressure shall be logged daily.

Principal header and component isolation valves shall be checked open at intervals no greater than three months.

~~. j,';,rgb y>~~"',>rW 3-Raw Service Water S stem Testin

<IV LIMITING I

CONDITIONS FOR OPEPATION SURVEILLANCE RE3UZREtWNTb 3'1 FIRE PROTECTION SySTEMS 4

11 FIRE PROTECTION SYSTE!viS Zf CO fir~

prot e<. tion i lo..t to a cable spreading room or to any diesel generat:or building area a continuous fire wI<tch shall be est abl is)><<<l immediately and shall be continued until CO q fire protection is restored.

C 5.

Fire Removal of any component in the CO<

Fire Protec tion System from service for any rea on other than testing or emergency op rations shall require Plant Manager approva x.

Detectors C.

Fire De ectors

~

V 2 ~

The fire detectior<

SySL<'ml '>< at,><>I]

s<>>ok

~ ~

<1I'

< I'<':l <>r."

t I ~ <

~> ll l>r<><<<:tr. Il shall be operable except that one detector for a given protected zone may be inoperable for a period no greater than 30 days.

Zf speci fication

3. 11.C.

1 e.ln<<ot b

~

me t, a

i>a..ro1 ling fire watch will bo establi"hed to ensure that each protected zone or a rea with inoperable detecto:s is check< d at interva1s nn err at'r l'l.I t I

< > I I ~

~ "I~ '1<

I > <) I<<.

320 2.

All heat and'moke d>>tectnrs hall be st <.<1 i.n ac<"-.or)ance with i<><lu."ltr LI>l standards or oth r approved methods semiannually.

The non-Class A

sup rvised detector circuitry for those'detectors which provide alarm only will be tested once each month by actua ing the

. detector at the end of the line or-end of t'e branch such that the la rge st number o f circuit conductors wi 1 1.

1>~ ~ ".1>>>I:k< <i.

LZHZTZNC CONOZTZONS FOR OPEPATZON SURVEZLLANCE REQUZREHFNTS 11 PZRF.

Pf!Y1'A.'TTOH

. Y.,TFAS 4

11 FIRF.

PRAT'KCTZON SYSTE.!S The class A

supervi

~d detector alarm circuit-Mil.l be tested once each two months at the local pa ne1 s.

4 5.

Tli-c I rrn its between the. local panels in

a. 11

~ c. 3 and the main cont,rol room vill be tested mon tnly.

Smoke detector sensitivity Mill be checked in accordanc Mith manufacturer'~

instruction annually.

D. Deleted I

D, Deleted

LIMITINO CONDITIONS FOR OPERATIOH SURVEILLANCE REQUIREMENTS 3.11 FIRE PROTECTION SYSTFMS 4.11 FIRE PROTECTION SYSTFMS E.

Fire Protection S stems Ins ection E.

Fire Protection Systems Ins ections All fire barrier penetrations, including cahle penetration

barriers, Eire doors and Eire dampers, in fire xone boundaries protecting safety related areas shall be funct-ional at all times.

With one or more of the required fire barrier penetrations non-functional Mithin one hour es-tablish a continuocs fire awatch on at least one side of the affected penetration or verify thc OPERAllILITY of fire detect-ors on at least one side of the non-functional fire barrier and establish an hourly fire Match patrol until the Mork is com-pleted"and the barrier is re-stored to functional status.

F.

Deleted Each required fire barrier penetration shall be verified to be functional at least once per 18 months by a visual inspect-

ion, and prior to restoring a

Eire barrier to functional status follovinR repairs oz maintenance by performance of s visual in-spection of the sfEected fire barrier pcnctration.

Deleted 322

r

~

2 3.11 PASFS The High Pressure Fire and CO~ Fire Protection specifications are piovided in order to meet the preestablished levels of operability during a fire in either or all of the three units.

Requiring a patrolling fire watch with portable fire equipment if the automatic initiation is lost will provide (as does the automatic system) for early reporting and immediate fire fighting capability in the event of a fire occurrence.

The High Pressure Fire Protection System is supplied by four pumps (three electric driven and one diesel driven) aligned to the high pressure fire header.

The reactors may remain in operation for a period not to exceed 7

day's if three pumps are out of service.

If at least two pumps are not made operable in seven days or if all pumps are lost during this seven day period, the reactors will be placed in the cold shutdown condition"within 2k hours.

For the areas of applicability, the fire protection water distribution system minimum capacity of 2664

@pm at 250'ead at the fire pump discharge consists of the fhllowing design loads:

1.

Sprinkler System (0.30 gpm/ft2/4440 ft2 area) 1332 gpm 2.

1 1/2" Hand Hose Lines 200 gpm 3.

Raw Service l4ater Load

~1132 III TOTAL 2664 gpm The C02 Fire Protection System is considered operable with a minimum of 8 1/2 tons (0.5 tank)

C02 in storage for units 1 and 2: and a minimum of 3 tons (0.5 tank)

C02 in storage for unit 3.

An immediate and continuous fire watch in the cable spreading room or any diesel generator building area will be established if C02 fire protection is lost in this room and will continue until C02 fire protection is restored.

Tn assure close supervision of Eire protection system activities, the removal from service of any component in either the High Pressure Fire System or the C02 Fire protection System for any reason other than testing or emergency operatio'ns will require Plant Manager's approval.

Fairly reporting and immediate fire fighting capability in the event of a fire occurrence will be provided (as with automatic system) by requiring a patrolling fire watch if more than one detector for a given protected zone is inoperable.

326

~

~

5.

Daily tests of <<nnunciation lights and audible device.s axe.

performed as a routine operation function.

The CO>, system manufacturer recommends semiannual testing of Co~ system fire detection circuits.

In addition, operating

'ersonnel per'iodically inspect the plant during th'eir normal operating activities for fire hazards and other abnormal conditions.

smoke detectors will be tested "in-place>> using inert freon gas applied by a pyrotronics type applicator which is accepted throuqhout the industrial fire protection industry for testing products of combustion detectors. or by use of the blSA chemical smoke generators.

At the present time the manufacturers have only approved the use of "punk>> for creating smoke.

TVA will not use>>punk>>

for testing smoke detectors.

329

0

6.O 6.1 A.

The plant manager has onsite responsibilities for the safe operation of the faoility and shall report to the Site

'Director.

Xn the absence of the plant manager, a plant superintendent will assume his responsibilities.

B.

The portion of TVA management which relates to the operation of the plant is shown in Figure 6.1-1.

C.

The funotional organization for the operation o'f the station is shown in Figure 6.1-2.

D.

Shift manning requirements shall, as a minimum, be as desoribed in seotion 6.8.

E.

Qualifications of the Browns Ferry Nuolear Plant (BFN) management and operating staff shall meet the minimum aooeptable levels as desoribed in ANSI'-N18.1, "Seleotion and Training of Nuolear Power Plant Personnel,"

dated March 8, 1971.

The qualifications of the Health Physios Supervisor will meet or exoeed the minimum acceptable levels as desoribed in Regulatory Guide 1.8, revision 1, dated September 1975.

F.

Retraining and replacement training of station personnel shall be in accordance with ANSI N18.1, "Seleotion and Training of Nuolear Power Plant Personnel,"

dated March 8, 1971.

The minimum frequenoy of the retraining program shall be every two years.

G.

An industrial seourity program shall be maintained for the life of the plant.

6.2 The Manager of the Office of Nuolear Power is responsible for the safe operation of all TVA nuclear plants, including BFN.

Organizational units for the review of faoility operation shall be oonstituted and have the responsibilities and authorities listed below.

.A.

ZJIHHXQK The NSS shall funotion to provide independent review and audit oognizance of designated aotivities in the areas of:

a.

Nuolear power plant operations.

b.

Nuolear engineering.

332

o.

Chemistry and radioohemistry.

d.

Metallurgy.

e.

Instrumentation and oontrol.

f.

Radiologioal safety.

g.

Meohanical and eleotrical engineering.

h.

Quality Assuranoe praotioes.

2.

The NSS shall be responsible for the independent nuolear safety review program and oognizance of audits for all TVA nuolear plants.

3 ~

4.

All NSS and other TVA personnel who have been designated as reviewers shall have an academic degree in engineering or s physical science field, or the equivalent; and in addition, shall have a minimum of five years'echnical experience in one or more areas given in 6.2.A.l.

The Chief, NSS shall meet the same qualifications as reviewers, except that the minimum experience shall be six years.

Consultants to the NSS shall be utilized to provide expert advice as determined by the Chief, NSS.

5.

A minimum of three reviewers shall review eaoh of the subjects enoompassed by seotions 6.2.A.6 and 6.2.A.7.

6.

JKUZJf.

The NSS shall review; a.

The safety evaluations for (1) ohanges to procedures, equipment or systems and (2) tests or experiments oompleted under the provision of seotion 50.59, 10 CFR, to verify that such aotions did not constitute an unreviewed safety question.

b.

Proposed ohanges to procedures, equipment, or systems whioh involve an unreviewed safety question as defined in seotion 50.59, 10 CFR. 333

c ~

Proposed tests or experiments which involve an unreviewed safety question as defined in section 50.59, 10 CPR.

d.

Proposed changes to teohnical specifications or this operating license.

e ~

Violations of codes, regulations,

orders, technical specifioations, license requirements, or of internal procedures or instructions having nuclear safety significance.

Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuolear safety.

All reportable events.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affeot nuolear safety.

Reports and meeting minutes of the PORC.

7.

JQIDXLi Audits of unit aotivities shall be per formed under the oognizance of the NSS.

These audits shall encompass:

a 0 The conformance of unit operation to provisions contained within the teohnical specifications and applicable license conditions at least once every

.12 months.

b.

The performance, training and qualifications of the entire unit staff at least once every 12 months.

The results of aotions taken to correct deficienoies ooourring in unit equipment, structures, systems or method of operation that affeot nuolear safety at least once every 6 months.

d.

The performance of aotivities required by the Operational Quality Assurance Program to meet the oriteria of Appendix &," 10 CFR 50, at least once every 24 months, B ~

The Site Radiological Emergency Plan and implementing, procedures at least once every 12 months.

334

4

f.

The Plant Physioal Security Plan and implementing prooedures at least once every 12 months.

g.

Any other area of unit operation considered appropriate by the NSS or the Manager of the Office of Nuolear Power.

h.

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

An independent fire protection and loss prevention program inspeotion and audit shall be performed annually utilizing either qualified offsite lioensee personnel or an outside fire. protection firm.

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

k.

The radiological environmental monitoring program and the results thereof at least once every 12 months.

1.

The performance of aotivities required by the Quality Assurance Program to meet the oriteria of Regulatory Guide 4. 15, December 1977 at least once every 12 months.

m.

The performance of activities required by the Safeguards Contingency Plan to meet the oriteria of 10 CFR 73.40(d) at least once every 12 months.

8 JQEHMLVX The NSS shall report to and advise the Manager of the Offioe of Nuolear Power on those areas of responsibility specified in seotions 6.2.A.6 and 6.2.A.7.

9.

JEHKTR Reports of aotivities shall be prepared, appr oved, and distributed as indioated below:

a.

Results of reviews and of cognizance of audits, inoluding those encompassed by sections 6.2.A.6 and 6.2.A.7 above, shall be approved by the Chief,

NSS, and forwarded to the Manager of the Office of Nuclear Power at least quarterly.

b.

Audit reports encompassed by seotion 6.2.A.7 above, shall be forwarded to the Manager of the Office of

- Nuclear Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.

335

e

6.0 B.

HEHBRBZKR The PORC shall consist of the plant manager, or his representative, eleotrio mg.ntenance seotion supervisor, mechanical maintenance section supervisor, 1nstrument maintenance seotion supervisor, health physios super-visor, operations seot1on supervisor, engineering section supervisor, and quality assurance supervisor.

An 'acting"section supervisor or his designee may serve as an alternate committee member.

The plant manager will serve as chairman of the PORC.

His representative wQ.l serve as ohairman in the absence of the plant manager.

2.

The PORC shall meet at regular monthly intervals and for speoial meetings as called by the ohairman or as requested by individual members.

. 3.

QEHUlH The plant manager or his representat1ve, plus five of the seven other members, or their alternate, will constitute a quorum.

A member will be considered present if he is in telephone communication with the committee.

The PORC serves in an advisory capaoity to the plant manager and as an investigating and reporting body to Nuolear Safety Staff (NSS) in matters related to'safety in plant operations.

The plant manager has the final responsibility in determining the matters that should be referred to the NSS.

The responsibility of the committee will include:

a.

Review all standard and emergency operating and maintenance instructions and any proposed revisions

thereto, with prinoipal attention to provisions for safe operation.

b.

Review proposed ohanges to the teohnical specifications.

336

o.

Review proposed ohanges to equipment or systems having safety significance, or which may constitute "an unreviewed safety question" pursuant to 10 CFR 50.59.

d.

Investigate reported or suspeoted incidents involving safety questions, violations of the technical speci-fications, and violations of plant instruotions pertinent to nuolear safety.

e.

Review reportable

events, unusual

events, operating anomalies and abnormal performance of plant equipment.

f.

Maintain a general surveillance of plant activities to identify possible safety hazards.

g.

Review plans for speoial fuel handling, plant maintenance, operations, and tests or experiments which may involve speoial safety considerations, and the results thereof, where applioable.

(Deleted)

)

I, Review implementating procedures of the Radiological Emergency Plan and the Industrial Security Program on an annual basis.

Review adequaoy of employee training programs and recommend change.

5.

JUEHHEXXX The PORC shall be advisory to the plant manager.

6.

mumua Minutes shall be kept for all PORC meetings,,

7.

ZBRQDEBER Written administrative procedures for committee operation shall be prepared and maintained describing the method for submission and content of presentations to the committee, review and approval by members of committee

actions, dissemination of minutes, agenda and soheduling of meetings.

337

4

6.0

6. 3 JJJÃJHIBER A.

Detailed written prooedures, inoluding applicable oheokoff lists oovering items listed below shall be prepared,

approved, and adhered to.

1.

Normal startup, operation, and shutdown of the reactor and of all systems and oomponents involving nuolear safety of the facility.

2.

Refueling operations.

3.

Aotions to be taken to oorrect speoific and foreseen potential malfunctions of systems or components, inoluding responses to alarms, suspected primary system leaks and abnormal reaotivity ohanges.

4.

Emergenoy conditions involving potential or aotual release of radioactivity.

5.

Preventive or corrective maintenanoe operations whioh could have an affeot on the safety of the reactor.

6.

Surveillance and testing requirements.

7.

Radiation control procedures.

8.

Radiological Emergenoy Plan implementing procedures.

9.

Plant seourity program implementing procedures.

10.

Fire proteotion and prevention prooedures.

'B.

Mritten procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant manager before implementation.

Temporary ohanges to a prooedure whioh do not ohange the intent of the approved prooedure may be made by a member of the plant staff knowledgeable in the area affeoted by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor Operator license on the unit affected.

Such ohanges shall be documented and subsequently reviewed by PORC and approved by the plant manager.

338

C.

Drills on actions to be taken under emergenoy oonditions involving release of radioaotivity are specified in the Radiological Emergency Plan and shall be conduoted annually.

Annual drills shall also be conduoted on the aotions to be taken following failures of safety related systems or oomponents.

D.

Radiation Control Prooedures shall be maintained and made available to all station personnel.

These procedures shall show permissible radiation exposure and shall be oonsistent with the requirements of 10 CPR 20.

This radiation protec-tion program shall be organized to meet the requirements of 10 CFR 20 exoept in lieu of the "oontrol device" or "alarm signal" required by paragraph 20.203(c) of 10 CFR 20.

1.

Eaoh high radiation area in whioh the intensity of radiation is greater than 100 mrem/hr but less than 1,000 mrem/hr shall be barricaded and conspicuously

, posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Speoial Work Permit~a).

Any individual or group of individuals permitted to enter such areas shall be provided with; or accompanied by, one or more of the following.

a.

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

/

b.

A radiation monitoring device whioh 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 may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

o.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate

~a) Health Physics personnel, or personnel escorted by Health Physios personnel, in aocordance with approved emergenoy procedures, shall be exempt from the Speoial Work Permit issuanoe requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection prooedures for entry into high radiation areas.

339

0 6.0 o.

(oontinued):

monitoring device.

This individual shall be respon-sible for pr oviding positive oontrol over the activi>>

ties within the area and shall perform periodic radiation surveillanoe at the frequenoy specified by the faoility Health Physioist in the Special Work Permit.

~ ~ Each high radiation area in which the intensity of radiation is greater than 1,000 mrem/hr shall be sub)ect to the provisions of (1) above;

and, in addition, access to the source and/or area shall be secured by lock(s)..

The key(s) shall be under the administrative control of the shift engineer.

In the case of a high radiation area established for a period of 30 days or less, direct su'rveillance to prevent unauthorized entry may be sub-stituted for permanent access control.

340

6.0 6.4 e e e

The plant

~nagei; shall notify the NRC as specified in Seotion 50.73 to 10 CFR"Part 50 of the circumstances of any reportable event.

The event shall be reviewed by PORC prior to submittal of the repor t to NRC.

This report shall include an evaluation of the oause of the event and recommendations for appropriate aotion to prevent or reduce the probability of a repetition of the event.

6.5 Zf a safety limit is exceeded, the reaotor shall be shut down and reaotor operation shall not be resumed until authorized by the NRC.

A prompt report shall be made to the Site Director, and the

Chief, NSS.

A complete analysis of the oiroumstances leading up to and resulting from the situation, together with recommenda-tions to prevent a recurrence, shall be prepared by the PORC.

This report shall be submitted to the Site Director, the Manager of the Office of Nuclear Power, and the Chief, NSS.

Further reporting requirements of 10 CFR 50.36(c)(1) shall be met.

6.6 A.

Records and/or logs shall be kept in a manner convenient for review as indioated below:

1.

All normal plant operation 'inoluding suoh items as power level, fuel exposure, and shutdowns.

2.

Prinoipal maintenance aotivities.

3.

Reportable events.

Cheoks, inspections,

tests, and oalibrations of components and systems, inoluding suoh diverse items as source leakage.

5.

Reviews of changes made to the procedures or equipment or reviews of tests and experiments to comply with 10 CFR 50.59.

346

6.

Radioaotive shipments.

7.

Test results, in units of microcuries, for leak tests performed pursuant to Teohnioal Speoification 3.8. D.

8.

Record of annual physical inventory verifying aocountability of sources on record.

9.

Gaseous and liquid radioaotive waste released to the environment.

10.

Offsite environmental monitoring surveys.

11.

Fuel inventories and transfers.

12.

Plant radiation and contamination surveys.

13.

Radiation exposures for all plant personnel.

14.

Updated, correoted, and as-built drawings of the plant.

15.

Reactor coolant system in-service inspection.

16.

NSS reports of results of reviews and of cognizance of audits.

17.

Design fatigue usage evaluation.

a.

Moni,toring, recording, evaluating, and reporting requirements contained in 17.b, below will be met for various portions of the reactor coolant pressure boundary (RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Section IIIwas performed1 for the conditions defined in the design specification.

In this See paragraph N-415.2, ASME Section III, 1965 Edition.

347

I l

6.0 ADMINISTRATIVECONTROLS 6.8 Minimum Plant Staffin The minimum plant staffing for monitoring and conduct of operations is as follows.

1.

A licensed senior reactor operator shall be present at the site at all times when there is fuel in the reactor.

2.

A licensed reactor operator shall be in-the control room whenever there. is fuel in the reactor.

3.

A licensed senior reactor operator or SRO limited to fuel handling shall be in direct charge of a reactor refueling operation; i.e.,

able to devote full time to the refueling operation.

A health physics technician shall be present at the facility at all times there is fuel in the reactor.

5.

Two licensed reactor operators shall be in the control room during any cold startups, while shutting down the reactor, and during recovery from unit trip.

6.

Either the plant manager or a plant supei intendent shall have acquired the experience and training normally required for examination by the NRC for a Senior Reactor Operator's

License, whether or not the examination is taken.

In addition, either the operations supervisor or the assistant operaitons supervisor shall have an SRO license.

7.

A Shift Technical Advisor shall be present at the site at all times.

358

~

c>

GENERAL H<SAGER MhÃAGER OF POhER AND ENGINEERING OFFICE OF NUCLEAR PO'PER

6!CLEAF. SAFETY DIRECTOR OF OL'ALITY ASSURANCE SITE DIRECTOR BFNP

- SITE DIRECTOR SQNP SITE DIRECTOR h'BNP SITE DIRECTOR BLiP DIRECTOR OP, UCLEAR SERVICES

0 Site Director Functional Reporting

Manager, Operations Qualit Assurance'ivision of Quality Assurance Modifications Manager Site Services Manager Design Services Manager Quality Assurance Plant Manager Plant Compliance perations an Engineering uperintenden Maintenance uperintenden Operations Engineering Assistant Operations Group Supervisor Shift Crews Shift Engineer ASE UO AUO FIGURE 6,1-2 FACILITY ORGANIZATION

0

PROPOSED UNIT 2 TECHNICAL SPECIFICATION REVISIONS

Section

~Pe e Ne.

B.

Core Monitoring 305 C.

Spent Fuel Pool Water 305 D.

Reactor Building Crane '.

307.

E.

Spent Fuel Cask 307 F.

Spent Fuel Cask Handling-Refueling Floor e

e e

e e

308

3. 11/4. 11 Fire Proteotion Systems

~

~

~

~

~

~

~

315 A.

High Pressure Fire Protection System 315 B.

C02 Fire Protection System 319 C.

Fire Detectors.............

320 D.

(Deleted)

~

~

~

~

~

~

~..

321 E.

Fire Protection Systems Inspection 322 F.

(Deleted)

G.

Air Masks and Cylinders

~

~

~

~

~

~

322

~

~

~

~

~

~

~

~

323 H.

Continuous Fire Watch 323 I.

Open Flames, Welding, and the Cable Spreading Room Burning in

~

~

1 323 5.0 Ma)or Design Features 330 5.1 Site Features 330 5.2 Reactor 330 5.3 Reactor Vessel 330 5e4 Containment 330 6.0 5.5 Fuel Storage 5.6 Seismic Design Administrative Controls 6.1 Organization 6.2 Review and Audit iv 330 331 332 332 S32

~,

Section 6.3 Procedures

~Pa e No.

338 6.4 Actions to be Taken in the Event of a Reportable Occurrence in Plant Operation 346 6.5 Actions to be Taken in the Event a Safety Limit is Exceeded 346 6.6 Station Operating Records 346 6.7 Reporting Requirements 349 6.8 Minimum Plant Staffing 358

I

L]ST OF 1

USTRAT]OHS Figure Titie

~Po

~ ko.

2.1.1 APN Flow Refcrencc Scram and APRH Rod Bloc'k S e 't'tin9 s

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

13.

2.1-2

4. 1-1'

'-1 APIN Flow Bias Scram Ys Reactor Core Flow 26 Craphic Aid in the Selection of an Adequate interval Between Tests 49 System Unavai'lability.

119 3 ~ 4-1

3. 4-2 3.5.K-1 Sodium Pcntaborate Solution Volume Concentration Requirements Sodium Pentaborate Solution Temperature Requirements

~

~

~

~

MCPR Limits 130 139 172a 3.5.2 3.6o 1

Yif Factor o

~

~

~

~

~

~

~

~

~

~

~

~

~

Hinimum Temperature

'F Above Change in Trans Temperatur e

~

~

~. ~

~..

~

~

~

~

~

173 ient

~

~

~

o'9'.G-2 Change in Charpy V Transition Temperature Vs Neutron Exposure a

]95

'G

~ 1-1 6.1-2 6.7-1 6.3-1 361 362 363 (Deleted)

(Deleted)

~

o e.

~

~

~

~

364 Offsite Organization. for Facility Management and 'Zechnical Support Facility Organization

~

~

~

vii i

0 e

LXt1ITINC CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 1 1 FIRE PROTECTION SYSTE!h1S

4. 1 1 XRE PROT ION SYSTEM 2 ~

6.

If specif ic~tion

3. 11.A. l. a or

3. 11. A. l. b cannot be

met, a patrolling fire wa tch with portable fire equipment aVailable shall be established to insur; that eacn area where protection is lost is checked hourly.

If only one high pressure fire pump is oper ahl e, the reactors may remain in operation for a period not to exceed 7 days, provided the requirements of specification

3. 11.A. 1.b above are met.

If specification 3.11.A.3.".annot be

met, the reactors shall be placed in the cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Removal of any component in the High Pressure Fire Syst m

from service for any reason ot.her than testing or emergency operation - shall requi re Plant Hanager a ppr oval.

The Raw Service Water storace tank level shall be maintained above level 723'7" by the raw service water pump s ~

317 2 0 3 ~

4.

5.

Raw Se rvice Wa ter S stem Testing Fr uenc Once/yeaY Simulated a utoma tic and manual actua tion of raw service water pumps and operation of tank level switches The high pressure fire protection system pressure shall be logged daily.

Principal header and component isolation valves shall be checked open at intervals no greater than three months.

When it is determined that only one pump is

operable, that pump shall be demonstrated operable immediately and daily thereafter until specification

3. 11.A. 1. a can be met.

(h'hl(

hh

LINITING CONDITIONS FOIt OPEPATION SURVEILLANCF! RBQUIRENENTS

3. 1 I

FIRE PROTECTION SYSTEMS 4

'l 1 FIRE PROTECTION SYST 9S 4.

If CO2 fire protec:tion is lost to a cable sprearlinq room or t o any diesel genr: rat;or h<r i 1di.r<g area a corrtinuous fire watch shall.

br establ ishe d immediately and shall be continued untiI.

CO > fire protec tion is restored.

Fir <.

"2.

Removal of any compon nt in the COr Fire Protec tion Syst<,m from servic'or any reason other tha n te st. i nq or emr:.rqency opera r;iorrs shall re<Iuire Plant Manager approva 1.

A< tent.orn The lire

<I< tectior<

system'ea t anrl smoke detectors for all protects<i zones shall-he operable except that one detector for a given protected zone may be inoperable for a period no greater than 30 d<<ys.

If spe(:i, I icat.i.on

3. 11. C.

1 c.<rrru>t b>>'et, a

p<< trolling fire watch will be establish' to ensure tha t each protected zone or

.s rea with inoperabl e d: tectors is check<-.'d a t intervals no greater t.han one each hour.

320 C.

b'ir>> Detectors All heat and smoke detectors shall be tested in accordance with industrial s tan da rds or ot her approved methods semiannually.

Th non-Class A

supervis ~d detect or cir-.cuitry for those hler ector which provi I>> <<lhrr<r -only wil1 be tested onc each rr<onth by actua ting the detector at the end of the line or end of thr branch such that th>> large'-t number of circuit conductors wilT. be checked.

K 0

p)

LIflZTZhC CONDITIONS FOR OPEPATIOW SURVFILLhNCK RFOU IRL'HLNTS 11

'1tZRK PPC7l'FCTTOM SYSTEMS 1 1 FIRF PACE'ECTIO't4 SYSTEMS ISj'.

The class h

supervised detec or alarm circuits ~i11 be tested once each too months at the 1 oc a 1 pa ne 1 s.

4.

The circuits betMeen

" thv local panel.". in

4. 11. c. 3 and the main control room Mill be tested monthly..

D.

Deleted 5.

D.

Deleted Smoke detector sensitivity Mi.ll b!

checked in accordanc~

~1th manufacturer's instruction annually.

~'21

I

~

~

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.11 FIRE PROTI'.CTION SYSTFMS 4.11 FIRE PROTECTION SYSTFMS E.

Fire Protection S stems In ection All fire barrier penetrations, including cable penetration barriers, fire doors and fire dampers, in fire zone boundaries protecting safety related areas shall be funct-ional at all times.

With one or more of the required fire barrier penetrations non-functional uithin one hour es>>

tablish a continuons fire uatch on at least one side of the affected penetration or verify the OPERABILITY of fire detect-ors on at least one side of the non-functional fire barrier and establish an hourly fire uatch patrol until the uork is com-pleted and the barrier is re-stored to functional status.

Deleted E.

Fire Protection S stems Ins ections Each required fire barrier penetration shall be verified to be functional at least once per 18 months by a visual inspect-ion, and prior to restoring a

fire barrier to functional status follouing repairs or maintenance by performance of a visual in-spection of the affected fire barrier penetration.

322

The High Pressure Fire and C02 Fire Protection specifications are provided in order to meet the preestablished levels of operability during a fire in either or all of the three units.

Requiring a patrolling fire watch with portable fire equipment if the automatic initiation is lost will provide (as does the automatic system) for early reporting and immediate fire fighting capability in the event of a fire occurrence.

The High Pressure Pire Protection System is supplied by four pumps (three electric driven and one diesel driven) aligned to the high pressure fire header.

The reactors may remain in operation for a period not to exceed 7

days if three pumps are out of service.

If at least two pumps are not made operable in seven, days or if all pumps are lost during this seven day period, the reactors will be placed 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 />.

For the areas of applicability, the fire protection water distribution system minimum capacity of 2664 gpm at 250'ead at the fire pump discharge consists of the following design loads:

1.

Sprinkler System (0.30 gpm/ft2/4440 ft2 area) 2.

1 1/2" Hand Hose Lines 3.

Raw Service Water Load TOTAL 1332 gpm 200 gpm 1132 mm 2664 gpm The C02 Fire Protection System is considered operable with a minimum of 8 1/2 tons (0.5 tank)

C02 in storage for units 1 and 2: and a mi'nimum of 3 tons (0.5 tank)

C02 in storage for unit 3.

An immediate and continuous fire watch in the cable spreading room or any diesel generator building area will be established if C02 fire protection is lost in this room and will continue until C02 fire protection is restored.

To assure close supervision of fire protection system activities, the removal from service of any component in either the High Pressure Fire System or the C02 Fire Protection System for any reason other than testing or emergency operations will require Plant Manager's

'pproval.

Early reporting and immediate fire fighting capabilitv in the event of a fire'ccurrence wi11 be provided (as with automatic system) by requiring a

patrolling fire watch if more than one detector for a given protected zone

's inoperable.

326

~

~

a.

naily tests of.innunciation light and audible devices arc

'pcrtormed as a routine operation function.

h" COg. system manufacturer recommends semiannual tes inq of

(:o, "ystem fir~ d.tection circuits.

In addition, operating

- personnel periodically inspect the plant during their normal operatinq activities for fire hazards and other abnormal conditions.

smok~ d. tractors Mill be tested

~ "in-place" Vsing inert freon gas appl ical by a pyrotronics type applicator vhich is accepted throvqhout the ind>>strial fire protection indu try for testing product". of combustion detectors or by use of the HSA chemical smoke generators.

At the present time the manufacturers have only approved the >>se of "punk" for creating smoke. 'VA ~ill not use "punk" for testing smoke detectors.

329

6.0 6.1 A.

The plant manager has onsite responsibilities for the safe operation of the faoility and shall report to the Site Direotor.

In the absenoe of the plant manager, a plant superintendent will assume his responsibilities.

B.

The portion of TVA management which relates to the operation of the plant is shown in Figure 6.1-1.

C.

The funotional organization for the operation of the station is shown in Figure 6.1-2.

D.

Shift manning requirements shall, as a minimum, be as desoribed in seotion 6.8.

E.

Qualifications of the Browns Ferry Nuolear Plant (BFN) management and operating staff shall meet the minimum aoceptable levels as desoribed in ANSI-N18.1, <<Selection and Training of Nuolear Power Plant Personnel,>>

dated Maroh 8, 1971.

The qualifications of the Health Physics Supervisor will meet or exceed the minimum aooeptable levels as desoribed in Regulatory Guide 1.8, revision 1, dated September 1975.

F.

Retraining and replaoement training of station personnel shall be in accordance with ANSI N18.1, "Seleotion and Training of Nuclear Power Plant Personnel,"

dated Maroh 8, 1971.

The minimum fr equenoy of the retraining program shall be every two years.

G.

An industrial security program shall be maintained for the life of the plant.

6.2 The Manager of the Office of Nuolear Power is responsible for the safe operation of all TVA nuclear plants, inoluding BFN.

Organizational units for the review of faoility operation shall be constituted and have the responsibilities and authorities listed below.

A.

1.

ZQlETXQK The NSS shall function to provide independent review and audit cognizanoe of designated activities in the areas of:

a.

Nuclear power plant operations.

b.

Nuolear engineering.

332

6.0 o.

Chemistry and radiochemistry.

d.

Metallurgy.

e.

Instrumentation and oontrol.

f.

Radiological safety.

g.

Mechanical and eleotrical engineering.

h.

Quality Assuranoe praotioes.

2.

The NSS shall be responsible for 'the independent nuclear safety review program and cognizance of audits for all TVA nuclear plants.

3 ~

4 ~

All NSS and other TVA personnel who have been designated as'eviewers shall have an academic degree in engineering or

~

physical science Field, or the equivalent;- and in addition, shall have a minimum of five years'echnical experience in one or more areas given in 6.2.A.1.

The Chief, NSS shall meet the same qualifications as reviewers, except that the minimum experience shall be six years.

Consultants to the NSS shall be utilized to provide expert advice as determined by the Chief, NSS.

5.

A minimum of three reviewers shall review each of the sub)ects encompassed by sections 6.2.A.6 and 6.2.A.7.

6, ZBXEE The NSS shall review; a.

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

b.

Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in seotion 50.59, 10 CFR. 333

o.

Proposed tests or experiments which involve an unreviewed safety question as defined in seotion 50.59, 10 CFR.

d.

Proposed changes to teohnical specifications or this operating license.

e.

Violations of codes, regulations,

orders, technical speoifications, license requirements, or.of internal procedures cr instruotions having nuolear safety significance.

f.

Significant operating abnormalities or deviations from normal and expeoted performanoe of unit equipment that affeot nuolear safety.

g.

All reportable events.

h.

All recognized indioations of an unanticipated deficienoy in some aspeot of design or operation of struotures,

systems, or oomponents that could affeot nuclear safety.

i.

Reports and meeting minutes of the PORC.

7.

LURID Audits of unit aotivities shall be performed under the oognizance of the NSS.

These audits shall encompass:

a.

The oonformanoe of unit operation to provisions contained within the teohnioal speoifications and applicable license oonditions at least once every 12 months.

b.

The performance, training and qualifications of the entire unit staff at least once every 12 months.,

c.

The results of aotions taken to correot deficienoies ocourring in unit equipment, struotures, systems or method of operation that affect nuolear safety at least onoe every 6 months.

d.

The performance of aotivities required by the Operational Quality Assurance Program to meet the oriteria of Appendix W,>> 10 CFR 50, at least once every 24 months.

e.

The Site Radiological Emergenoy Plan and implementing procedures at least once every,l2 months.

334

4 0

f.

The Plant Physioal Security Plan and implementing procedures at least once every 12 months.

g.

Any other area of unit operation considered appropriate by the NSS or the Manager of the Office of Nuolear Power, h.

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

i.

An independent fire protection and'oss prevention program inspeotion and audit, shall be performed annually utilizing either qualified offsite lioensee personnel or an outside fire protection firm.

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

k.

The radiological environmental monitoring program and the results thereof at least once every 12 months.

1.

The performance of aotivities required by the Quality Assurance Program to meet the oriteria of Regulator y Guide 4.15, December 1977 at least once every 12 months.

The performance of aotivities required by the Safeguards Contingency Plan to meet the oriteria of 10 CFR 73.40(d) at least onoe every 12 months.

8.

ZuaaaXxX The NSS shall report to and advise the Manager of the Office of Nuolear Power on those areas of responsibility speoified in seotions 6.2.A.6 and 6.2.A.7.'.

JERBXG.

Reports of activities shall be prepared,

approved, and distributed as indioated below:

a.

Results of reviews and of cognizanoe of audits, inoluding those encompassed by seotions 6.2.A.6 and 6.2.A.7 above, shall be approved by the Chief,

NSS, and forwarded to the Manager of the Office of Nuolear Power at least quarterly.

b.

Audit reports enoompassed by seotion 6.2.A.7 above, shall be forwarded to the Manager of the Office of Nuolear Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.

335

0

6.0 B.

HEHKBZKR The PORC shall consist of the plant manager, or his representative, electricimaintenance seotion supervisor, meohanical maintenance section supervisor, 1nstrument maintenance seotion supervisor, health physics super-visor, operations seotion superv1sor, engineering section supervisor, and quality assuranoe supervisor.

An 'acting section supervisor or his designee may serve as an alternate oommittee member.

The plant manager w111 serve as ohairman of the PORC.

His representative will serve as ohairman in the absence of the plant manager.

2.

The PORC shall meet at regular monthly intervals and for spec1al meetings as oalled by the chairman or as requested by individual members.

3.

2KEE The plant manager or his representative, plus five of the seven other members, or their alternate, will constitute a quorum.

A member will be considered present if he is in telephone oommunioation with the oommittee.

4, The PORC serves in an advisory oapaoity to the plant manager and as an investigating and reporting body to Nuolear Safety Staff (NSS) in matters related to safety 1n plant operat1ons.

The plant manager has the final responsibility in determin1ng the matters that should be referred to the NSS.

The responsibility of the committee will inolude:

a.

Review all standard and emergenoy operating and maintenanoe instruotions and any proposed revisions

thereto, with prinoipal attention to provisions for safe operation.

b.

Review proposed changes to the teohnical spec1fications.

336

c.

Rev1ew proposed ohanges to equipment or systems having safety significanoe, or whioh may constitute "an unreviewed safety question>>

pursuant to 10 CFR 50.59.

d.

Investigate reported or suspeoted incidents involving safety questions, violations of the technical" speoi-f1cations, and violations of plant instruotions pertinent to nuolear safety.

e.

Review reportable

events, unusual

events, operating anomalies and abnormal performanoe of plant equipment.

f.

Maintain a general surveillanoe of plant aotivit1es to identify possible safety hazards.

g.

Review plans for speoial fuel handling, plant maintenance, operations, and tests or experiments whioh may involve speoial safety considerations, and the results thereof, where applicable.

(Deleted)

P ~

Review implementatlng procedures of the Radiological Emergency Plan and the Industrial Security Program on an annual basis.

Review adequaoy of employee training programs and reoommend ohange.

5.

SRQKNIXX The PORC shall be advisory to the plant manager.

6.

2KQQKR Minutes shall be kept for all PORC meetings.

.7.

EKQEIHlRER 4

Written administrative procedures for comm1ttee operation shall be prepared and maintained desoribing the method for submission and oontent of presentations to the oommittee, review and approval by members of committee

actions, dissemination of minutes, agenda and soheduling of meetings.

337

e

A.

Detailed written procedures, including applicable oheckoff lists covering items listed below shall be prepared,

approved, and adhered to.

1.

Normal startup, operation, and shutdown of the reactor and of all systems and oomponents involving. nuolear safety of the facility.

2.

Refueling operations.

3.

Actions to be taken to correct specifio and foreseen potential malfunctions of systems or components, including responses to alarms, suspeoted primary system leaks and abnormal reaotivity changes.

Emergency conditions involving potential or actual release of radioaotivity.

5.

Preventive or corrective maintenance operations which could have an affect on the safety of the reaotor.,

6.

Surveillance and testing requirements.

7.

Radiation control procedures.

8.

Radiological Emergency Plan implementing procedures.

9.

Plant security program implementing procedures.

10.

Fire protection and prevention procedures.

B.

Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant manager before implementation.

Temporary changes to a procedure which do not ohange the intent of the approved procedure may be made by a member of the plant staff knowledgeable in the area affeoted by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reaotor Operator license on the unit affeoted.

Such changes shall be dooumented and subsequently reviewed by PORC and approved by the plant manager.

338

C.

Drills on aotions to be taken under.emergency conditions involving release of radioaotivity are specified in the Radiological Emergency Plan and shall be conducted annually.

Annual drills shall also be oonduoted on the aotions to be taken following failures of safety related systems or components.

D.

Radiation Control Procedures shall be maintained and made available to all station personnel.

These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.

This radiation protec-tion program shall be organized to meet the requirements of.

10 CFR 20 exoept in lieu of the "oontrol device" or "alarm signal" required by paragraph 20.203(o) of 10.CFR 20.

Eaoh high radiation area in which the intensity of

.- radiation is greater than 100 mrem/hr but less than 1,000 mrem/hr shall be barricaded and oonspiouously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Speoial Work Permit(a).

Any individual or group of individuals permitted to enter suoh areas shall be provided with, or accompanied by, one or more of the following.

a.

b.

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

A radiation monitoring device whioh oontinuously 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 may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

o.

An individual qualified in radiation proteotion procedures who is equipped with a radiation dose rate (a) Health Physics personnel, or personnel esoorted by Health Physics personnel, in aocordance with approved emergenoy procedures, shall be exempt from the Speoial Work Permit issuance requirement during the performance of their assigned radiation proteotion duties, provided they oomply with approved radiation proteotion pr ooedures for entry into high radiation areas.

339

~

6.0 o.

(oontinued):

monitoring device.

This individual shall be respon-sible for providing positive oontrol over the aotivi-ties within the area and shall perform periodio radiation surveillanoe at the frequency speoified by the faoility Health Physioist in the Speoial Work Permit.

2. Each high radiation area in which the intensity of radiation is greater than 1,000 mrem/hr shall be sub)ect to the provisions of (1) above;

and, in addition, access to the source and/or area shall be secured by lock(s).

The key(s) shall be under the administrative control of the shift engineer.

Xn the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be sub-stituted for permanent access control.

0

6.0 The plant manager shall. notify the NRC as specified in Section 50.73 to 10 CFR Part 50 of the circumstanoes of any reportable event.

The event shall be reviewed by PORC. prior to submittal of the report to NRC.

This report shall inolude an evaluation of the cause of the event and recommendations for appropriate action to prevent or reduce the probability of a repetition of the event.

6.5 Zf a safety limit is exoeeded, the r eaotor shall be shut down and reactor operation shall'ot be resumed until authorized by the NRC.

A prompt report shall be made to the Site Director, and the

Chief, NSS.

A complete analysis of the oiroumstances leading up to and resulting from the situation, together with recommenda-tions to prevent a recurrence, shall be prepared by the PORC.

This report shall be submitted to the Site Director, the Manager of the Office of Nuolear Power, and the Chief, NSS.

Further reporting requirements of 10 CFR 50.36(c)(1) shall be met.

6.6 A.

Records and/or logs shall be kept in a manner convenient for.-

review as indioated below:

1.

All normal plant operation inoluding suoh items as power.

level, fuel exposure, and shutdowns.

2.

Prinoipal maintenanoe aotivities.

3.

Reportable events.

Cheoks, inspeotions,

tests, and oalibrations of components and systems, inoluding suoh diverse items as.

source leakage.

5.

Reviews of ohanges made to the prooedures or equipment or reviews of tests and experiments to comply with 10 CFR 50.59.

346

0,

'l

e 6.

Radioaotive shipments.

7 ~

Test results, in units of miorocuries, for leak tests performed pursuant to Teohnical Speoification 3.8.9.

8.

Record of annual physical inventory verifying aocountability oi sources on record.

9.

Gaseous and liquid radioaotive waste released to the environment.

10.

Offsite environmental monitoring surveys.

11.

Fuel inventories and transfers.

12.

Plant radiation and contamination surveys.

13.

Radiation exposures for all plant personnel.

14.

15.

Updated, correoted, and as-built drawings of the plant.

Reaotor coolant system in-service inspection.

16.

NSS reports of results of reviews and of cognizance of audits.

17.

Design fatigue usage evaluation.

a.

Monitoring, recording, evaluating, and reporting requirements contained in 17.b, below will be met for various portions of the reactor coolant pressure boundary (RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Section IIIwas performed> for the conditions defined in the design speoification.

In this 1See paragraph N-415.2, ASME Section III, 1965 Edition.

347

)

e 6.'0 ADMINISTRATIVE CONTROLS'.8 Minimum Plant Staffing The minimum plant staffing for monitoring and conduct of operations is as follows.

1.

A licensed senior reactor operator shall be present at the site at all times when there is fuel in the reactor.

2.

A licensed reactor operator shall be in the control room whenever there is fuel in the reactor.

3.

A lioensed senior reactor operator or SRO limited to fuel handling shall be in direct charge of a reactor refueling operation; i.e.,

able to devote full time to the refueling operation.

4.

A health physics technician"shall be present at the facility at

'll times there is fuel in the reactor.

5.

Two licensed reactor operators shall be in the control room during any cold startups, while shutting down the reactor, and during r ecovery from unit trip.

6.

Either the plant manager or a plant superintendent shall have acquired the exper ience and training normally required for'xamination by the NRC for a Senior Reactor Operator's

License, whether or not the examination is taken.

In addition, either the operations supervisor or the assistant operaitons supervisor shall have an SRO license.

"f.

A Shift Technical Advisor shall be present at the site at all times.

358

0 0

O O

& M M OOQ KKC IMW OO COW I CO W M pl GENERAL H44ACER

%WAGER OF POtiER AND ENGINEERING OFFICE OF NUCLEAR POWEi?

hUCLEAR SAFETY C~q ZT'IRECTOR OF QUALITY ASSURANCE SITE DIRECTOR BFNP SITE DIRECTOR SQNP SITE DIBECTOR VBXP SITE DIRECTOR BLNP DIRECTOR 0~

'UCLEAR SERVICES

0'

Site Director Functional Reporting

Manager, Operations Quality Assurance Division of Quality Assurance Modifications Manager Site Services Manager Design Services Manager Quality Assurance Plant Manager Plant Compliance perations an Engineering uperintenden Maintenance uperintenden Operations Engineering Assistant Operations Group Supervisor Shift Crews Shift Engineer ASE UO AUO FIGURE 6.1-2 FACILITY ORGY'IIZATION

e

PROPOSED UNIT 3 TECHNICAL SPECIFICATION REVISIONS

0

Section 3 10/4 10 C..Operation in Cold Shutdcwn Core Alterations

$>acCe Ho.

326 331 B

C ~

D ~

Refueling Znteriucks Core Monitoring Spent Fuel Pool Water Reactor Building Crane Spent Fuel Cask Spent Fuel Cask Handling-Refueling Floor 331 33 6'37 338 339 339 3 ~ 11/4i 11 Fire Protection Systems 347 Bi C

High Pressure Fire Protection System CO ~ Fire Protection System Fire Detectors 347 351 352 D

Deleted E.

Fire Protection Systems Inspections F ~

Deleted G.

Air Masks and Cylinders H.

Continuous Fire Watch 353 354 355 355 5

0 I.

Open Flames, Welding,.and Burning in the Cable Spreading Room Major Design Features

5. 1 Site Features 5.2 Reactor 5.3 Reactor Vessel

5. 4 Cont'ainment 355 360 360 360 360 360 6.0 5.5 Fuel Storage 5.6 Seismic Design Administrative Controls

6. 1 Organization

- 360 361 362 362 iv

LIST OF ILLUSTRATIONS Figure 2 1-1

2. 1-2

4. 2" 1

3. 4" 1 3 ~ 4-2 Title APRM Flow Reference Scram and APRM Rod Block Settings APRM Flow Bias Scram Relationship to Normal Operating Conditions Graphic Aid in the Selection of an Adequate Interval Between Tests System Unavailability Sodium Pentaborate Solution Volume Concentration Requirements Sodium Pentaborate Solution Temperature Requirements 14 25 48 117 141 142 3.5.K-1

3. 5. 2 3.6-1 3, 6-2 6.1-1

6. 1-2

6. 2-1 6.3>>1 P

MCPR Limits Kg Factor vs. Percent Core Flow Temperature-Pressure Limitations Change in Charpy V Temperature vs.

Neutron Exposure Offsite Organization for Facility Management and Technical Support Facility Organization D'eleted Deleted 182c 183 207 208 391 392 393 394

~,

LINXTING CONDITXONS FOR OPSQRTMS SQENKXLXIASCE RPQDIRElCWTS 2 ~

6 ~

T f sp cificaticm

3. 11.A. 1. a or 3.11.A.l.b cannot be

met, a patrolling fire watch with portable fire equi pment available shall be established to insure that each area Were protection is lost is checked houz, ly.

Tf only one high pressure fire purrrp is

operable, the reactors may remain in operation for a period not to ercceed 7 days, provided the requirements of specification 3.11.A.1.b above are met.

If specif ication 3.11.A.3 cannot be met, the reactors shall h

. placed in tho cold shutdown condition in 2¹ hours.

Removal of any.

• component in the High

- Pressure Fire System from service for any reason other than testing or emergency operations shall require Plant Manager approval.

The Ra+ Service Mater storage tank level shall be maintained above level 723 ~ 7" by the ra~ service eater oul%p so 3H 2 ~

when it is Octo.rrrrine".

that only one oump is operable~ that purrrp shall be demonstrated op rabble irrrme'diatelv and daily thereafter until specification 3.11 A.1.a can be mete

'5 Frc!~uence IXtem s irrrulated automatic and.manual, actuation of r~ service eater pcs and operation of tank level switches Oncei yea r The high pressure fire protection system pressure shall be logged daily.

Principal header and ccxaponent isdlation valves shall be checked open. at intervals no greater than three months.

3.

Ra~ Serv ce Mat r

~,

LINrTXRG COMQXTXGHS POR OPQLQRXCN SQRVRXKJALRCE R2QUXREFKIRS 3 ~ 1 f FIRE PROT'~Z 8 8~

~'l0 R

~f co~ f'ire protection is lost to a cable sprend inc roce or to any diesel generator buJi.ldincj area a contiILeoue fire vetch shall be est,abl ished immediately and ahall

'e cc:ntinued until CO> <ire protection i8 r+'storedo 5.

Removal of any ccaapon~t in the CQ>

Fire Pro=ecMon System fr+a service fo>> arsy reason other shan testing or, emexgency opezaticR1$

shall require Plant Nanagei apprcrgal~

ZLB Pire Detectors 2 ~

The fir~ detection system~s b~at and smoke dc.tectors for all protected cameo shall be operable except, that one detector for a given protected xone cmy be inoperable for a

,period.no greater

'than 30.days Zf specification 3.1).C 1 cannot be

swt, a patrolling fixe watch will be established to ensure that each'. protected mone or area with inoperabl e detectoro io checked at interva1s no grooter than one each hour.

All heat and evoke detectors shall he

'ered in accordance

~ith industrial standards or ot,her approved methods semiannually 2 ~

The non-Class A

supervise detector circuitry for those detectors which provide alarm only wi11 be tested once each cath by actuating the detector at the end of the line or end of the branch such that the Iarcgoot n~bor of circuit. conductors will be cheeked

LRi%XTING CONQITIONS POR OISINTICN 5QilVEILLNK!IREQUIIRNESTS

9. 1 0 RE PROPZCTTON SYS 4 ~ 11 RF.

R The class h supervised detector alara circuits vill be tested once each two saanths at the local panels.

The circuits bet>veen the local panels in 4.11.c.3 and the aain control rcxe %11 be tested senthly.

5 Swee detector sensitivity vill be checked in accordance with aanufacturer~s instruction annuallY-i Deleted D

i Deleted qi!v Pi 3S3

IJ\\

I 0

~ LIMITING'ONDITIONSFOR OPERATION AUG 2V 1984 SURVEILLANCE RKDUIREMENTS 3.11 FIRE PROTFCTION SYSTFAS 4 ~ 11 FIRE PROTECTION SYSTFMS E.

Fire Protection Systems Inspection E.

Fire Protection Systems Inspections All fire barrier penetrations, includinp cable penetration barriers, fire doors and fire dampers, in fire tone boundaries protecting safety related areas shall be funct-ional at all times.

With one or more of the required fire barrier penetrations non-functional Mithin one hour es-tablish a continuons fire awatch on at least one side of the affected penetration or verify the OPERABILITY of fire detect-ors on at least one side of the non-functional fire barrier and establish an hourly fire Match patrol until the Mork is com-pleted and the barrier is rc.

stored to functional status.

Each required fire barrier penetration shall be verified to be functional at least once per 18 months by a visual. in pect-

ion,

'and prior to restoring a

fire barrier to functional status folloving repairs or maintenance

~ by performance of a visual in-

. spection of the affected fire barrier penetration.

Deleted 354

R

$. 11

,BASES The High Pressure Fire and CO Fire Protection specif'ications are pr ovided in order to meet the preestablished level" of operability during a fire in either or all of the three units.

Requiring a patrolling fire awatch with portable f'irc equipment if'he automatic initiation is lost will provide (as does the automatic system) for early reporting and immediate f'ire fighting capability in the event of a t'ir e occurrence.

Thc High Pressure Fire Protection System is supplied by f'our pumps (three electric dr iven and one diese3 dr iven) aligned to the high prcssure f'irc

.header.

Thc reactors may remain in operation for a period no to exceed 7

days if three pumps are out of service.

If at least two pumps are not made operable in seven days or if'llpumps are lost during this'even day pe'riod,

, the reactor" will be placed 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 />.

For the areas of'pplicability, the fire protecticn water distribution system minimum capacity of 2664 gpm at 250'ead at the fire pump discharge consists of the f'ollowing design loads:

1.

Sprinkler System (0.30 gpm/ft /4440 ft area) 2 2

2.

=1 1/2" Hand Hose Lines 3.

Raw Service Mater Load TOTAL 1332 grm 200 gpm 1132

.6 4 gpm Thc CO Fire Protection System is considered operable 'rith a mirlmum 'of'

'1/2 tnns (0.5 tank)

C02 in storage for units 1 and 2; and

." minimum f 3 tons (0.5 tank)

C02 fn stor.inc for unit 3.

An immediate an continuous fire awatch in the cable spreading room or any diesel generator buxlding are.- will be established if C02 fire protection is lost in th's room and will continue until CO fire protection is restored.

To assure close supervision of f'ire protection system activities, the removal f'rom service of any component in either the High Pressure Fire System or the C02 Fire Protection Sys" em t'or any reason other than testing" or emergency opera'ona will require Plant

>fanager approval.

Farly reporting and immediate fire fighting capability in the event nf a fire occurrence will be provided (as with the automatic system) by requiring a

patrolling fire watch if more than one detector for a given protected zone id '.nnoerable.

356

0

Aailv tests of annunciation lights and.audible devices are performed as a routine operation function.

5.

he CO> system manufacturer recommends seed.annual testing of CO> system fire detection circuits En addition, operating personnel periodically inspect the plant. during their normal operating activities for fire hazards and other abnormal conditions.

Smoke detectors. vill be tested "in-place" using inert freon gas applied by a pyrotronics type applicator othich is accepted throughout the industrial fire protection industry for testing products of combustion detectors or by use of the NSA chemical smoke generators..'t the present time the manufacturers have only approved the.'use of "punk" for creating smoke.

TVA vill not use

<punk> for testing smoke detectors.

359

li

A.

The plant manager has onsite responsibilities for the safe operation of the faoility and" shall report to the Site Director.

In the absence of the plant manager, a plant superintendent will assume 'his responsibilities.

B.

The portion of TVA management which relates to the operation of the plant is shown in Figure 6.1-1.

C.

The functional organization for the operation of the station is shown in Figure 6.1-2.

D.

Shift manning requirements shall, as a minimum, be as desoribed in section 6.8.

E.

Qualifications of the Browns Ferry Nuolear Plant (BFN) management and operating staff shall meet the minimum acceptable levels as desoribed in ANSI-N18.1, "Seleotion and Training of Nuclear Power Plant Personnel,"

dated March 8, 1971.

The qualifications of the Health Physics Supervisor will meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, revision 1, dated September 1975.

F.

Retraining and replacement training of station personnel shall be in accordance with ANSI N18.1, "Seleotion and Training of Nuclear Power Plant Personnel,"

dated March 8, 1971.

The minimum frequency of the retraining program shall be every two years.

G.

An industrial seourity program shall be maintained for the life of the plant.

6.2 The Manager of the Office of Nuclear Power is responsible for the safe operation of all TVA nuolear plants, including BFN.

Organizational units for the review of faoility operation shall be constituted and have the responsibilities and authorities listed below.

E/HQXXQK The NSS shall function to provide independent review and audit oognizance of designated activities in the areas of:

a.

Nuclear power plant operations.

b.

Nuolear engineering.

362

II n,

6.0 o.

Chemistry and radiochemistry.

d.

Metallurgy.

e.

Instrumentation and oontrol.

f.

Radiological safety, g.

Meohanical and electrical engineering.

h.

Quality Assuranoe practices.

2.

The NSS shall be responsible for the independent nucclear safety review program and cognizance of audits for all.,

TVA nuclear plants.

4 ~

IJEIWX2M All NSS and other TVA personnel who have been designated as reviewers shall have an academic degree in engineering"or a'hysical science field, or the equivalent;. and in addition,~

shall have a minimum of five years'echnical experience in one or more areas given.:in 6.2.A.1.

The Chief, NSS shall meet the same qualifications as reviewers, except that the minimum experience shall be six years.

Consultants to the NSS shall be utilized to provide expert advice as determined by the Chief, NSS.

5.

A minimum of three reviewers shall review each of the subjects encompassed by sections 6.2.A.6 and 6."2.A.7.

6.

ZxtZaK The NSS shall review; a.

The safety evaluations for (1) ohanges to procedures, equipment or systems and (2) tests or experiments oompleted under the provision of seotion 50.59, 10 CFR, to verify that such aotions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in seotion 50.59, 10 CFR. 363

o.

Proposed tests or experiments which involve an unreviewed safety question as defined in seotion 50.59, 10 CPR.

d.

Proposed ohanges to teohnical speoifications or this operating license; e.,

Violations of codes, regulations,

orders, technical speoifications, license requirements, or of internal procedures or instruotions having nuolear safety significance.

f.

Significant operating abnormalities or deviations from normal and expeoted performance of unit equipment that affeot nuolear safety.

g.

All reportable events.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of

~ structur es,

systems, or components that could affeot nuolear safety.

Reports and meeting minutes of the PORC.

7.

392XXR Audits of unit aotivities shall be performed under the cognizance of the NSS.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the teohnioal speoifications and applioable,license conditions at least once every 12 months.

b.

The performance, training and qualifications of the entire unit staff at least once every 12 months.

c.

The results of aotions taken to correct deficienoies ooourring in unit equipment, struotures, systems or method of operation that affect nuolear safety at least once every 6 months.

d.

The performanoe of activities required by, the Operational Quality Assurance Program to meet the criteria of Appendix M," 10 CPR 50, at least onoe every 24 months.

e.

The Site Radiologioal Emergency Plan and implementing procedures at least once every 12 months.

360

6.0 f.

The Plant Physical Security Plan and implementing procedures at least onoe every 12 months.

Any other area of unit operation oonsidered appropriate by the NSS or the Manager of the Office of Nuolear Power.

h.

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

i.

An independent fire proteotion and loss prevention program inspeotion and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire proteotion firm.

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

k.

The radiological environmental monitoring program and the results thereof at least once every 12 months.

1.

The performance of aotivities required by "the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 at least once every 12 months.

m.

The performance of aotivities required by the

. Safeguards Contingenoy Plan to meet the criteria of 10 CFR 73.40(d) at least onoe every 12 months.

8 JUlXHEKXX The NSS shall report to and advise the Manager'of the Office of Nuolear Power on those areas of responsibility specified in seotions 6.2.A.6 and 6.2.A.7.

9.

3KP01tLR Reports of aotivities shall be prepared,

approved, and-distributed as indioated below:

a.

Results of reviews and of cognizance of audits, inoluding those encompassed by seotions 6;2.A.6 and 6.2.A.7 above, shall be approved by the Chief,

NSS, and forwarded to the Manager of the Office of Nuclear Power at least quarterly.

0 b.

Audit reports encompassed by section 6.2.A.7 above, shall be forwarded to the Manager of the Office of Nuolear Power and to the management positions responsible for the areas audited within 30 days after completion of the audit.

365

I

HEHBRRKXR The PORC shall consist of,'the plant manager, or his representative, eleotricAmaintenance seotion supervisor, mechanical maintenanoe se'ction supervisor, instrument maintenance seotion superv1sor, health physi'os super-v1sor, operations seotion supervisor, engineering seotion supervisor, and quality assuranoe supervisor.

An acting section supervisor or his designee may serve as an alternate committee member.

2.

The plant manager will serve as ohairman of the PORC.

His representative will serve as ohairman in the absenoe of the plant manager.

I I

The PORC shall meet at regular monthly intervals and for speoial meetings as oalled by the ohairman or as requested by individual members.

3.

MQR!E The plant manager or his representative, plus five of the seven other members, or their alternate, will oonstitute a quorum.

A member w111 be considered present if he is 1n telephone communication with the oommittee.

4.

The PORC serves in an advisory capaoity to the plant manager and as an 1nvestigating and reporting body to Nuolear Safety Staff (NSS) in matters related to safety in plant operations.

The plant manager has the f1nal responsibility in determining the matters that should be referred to the NSS.

The responsibility of the oommittee will 1nolude:

a.

Review all standard and emergenoy operating and maintenanoe instructions and any proposed revisions thereto, with pr1noipal attention to provisions for safe operation.

b.

Review proposed ohanges to the teohnical speoifications.

366

U

0 6.0 c.

Review proposed changes to equipment or systems having safety signif1oance, or whioh may constitute "an unreviewed safety quest1on" pursuant to 10 CFR 50.59.

d.

Investigate reported or suspeoted inoidents involving safety questions, violations of the teohnical speoi-fications, and violations of plant instructions pertinent to nuolear safety.

e.

Review reportable

events, unusual

events, operating anomalies and abnormal performance of plant equipment.

f.

Maintain a general surveillanoe of plant aotivities to identify possible safety hazards.

g.

Review plans for spec1al fuel handling, plant maintenance, operat1ons, and tests or experiments wh1oh may involve speoial safety considerations, and the results thereof, where applicable.

(Deleted)

Rev1ew implementating procedures of the Radiological Emergenoy Plan and the Industrial Security Program on an annual basis.

Review adequacy of employee training programs and recommend change.

5.

SllXHQBIXX The PORC shall be advisory to the plant manager.

6.

%KERR Minutes shall be kept for all PORC meetings.

7 ZBKIREKR Written administrative prooedures for oommittee oper ation shall be prepared and maintained desoribing the method for submission and oontent of presentations to the committee, review and approval by members of oommittee

aotions, dissemination of minutes, agenda and scheduling of meetings.

367

Detailed written procedures, inoluding applicable oheckoff lists covering items listed below shall be prepared,

approved, and adhered to.

1.

Normal startup, operation, and shutdown of the reactor and of all systems and oomponents involving nuolear safety of the faoility.

2.

Refueling operations.

3.

Aotions to be taken to correot speoifio and foreseen potential malfunotions of systems or oomponents, inoluding responses to alarms, suspected primary system leaks and abnormal reaotivity changes.

4.

Emergenoy conditions involving potential or aotual release of radioaotivity.

5.

Preventive or corrective maintenanoe operations which could have an affect on the safety of the reaotor.

6.

Surveillance and testing requirements.

7.

Radiation oontrol procedures.

8.

Radiological Emergenoy Plan implementing procedures.

9'.

Plant seourity program implementing procedures.

10.

Fire proteotion and prevention procedures.

Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant manager before implementation.

Temporary changes to a procedure which do not ohange the intent of the approved prooedure may be made by a member of the plant staff'knowledgeable in the area affeoted by the procedure except that temporary changes

'o those items listed above exoept item 5 require the additional approval of a member of the plant staff who holds a Senior Reaotor Operator license on the unit affected.

Such changes shall be documented and subsequently reviewed by PORC and approved by the plant manager.

368

1 ~

e" C.

Drills on aotions to be taken under emergency conditions involving release of radioactivity are specified in the Radiological Emergenoy Plan and shall be conduoted annually.

Annual drills shall also be conducted on the actions to be taken following failures of safety related systems or components.

D.

Radiation Control Procedures shall be ma1ntained and made available to all station personnel.

These prooedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.

This radiation proteo-tion program shall be organized to meet the requirements of 10 CFR 20 except in lieu of the "control dev1ce" or "alarm signal" required by paragraph 20.203(c) of t0 CFR 20.

1.

Eaoh high radiation area in which the intensity of rad1ation is greater than 100 mrem/hr but less than 1,000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Speoial Work Permit~a).

Any individual or group of individuals permitted to enter suoh areas shall be provided with, or accompanied by, one or more of the following.

a.

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

b.

A radiation monitor1ng 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 may be made afte'r the dose rate level in the area has been established and personnel have been made knowledgeable of them.

o.

An individual qualified in radiation protection procedures who is equipped with a radiation dose rate

~a) Health Physics personnel, or personnel escorted by Health Physics personnel, in accordance with approved emergenoy procedures, shall be exempt from the Special Work Permit issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation proteotion procedures for entry into high radiation areas.

369

o, (oontinued):

monitoring device.

This individual shall be respon-sible for providing positive control over the activi-ties within the area and shall perform periodio radiation surveillanoe at the frequency specified by the faoility Health Physicist in the Special Work Permit.

2 'ach high radiation area in which the intensity of radiation is greater than 1,000 mrem/hr shall be sub)ect to the provisions of (1) above;

and, in addition, access to the source and/or area shall be secured by lock(s).

The key(s) shall be under the administrative control of the shift engineer.

In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be sub-stituted for permanent access control.

370

P

h 6.0 The plant manager shall notify the NRC as specified in Seotion 50.73 to 10 CFR Part 50 of the oiroumstances of any reportable event.

The event shall be reviewed by PORC prior to submittal of the report to NRC.

This report shall include an evaluation of the cause of the event and recommendations for appropriate action, to prevent or reduce the probability of a repetition of the event.

6.5 Zf a safety limit is exoeeded, the reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC.

A prompt report shall be made to the Site Director, and the

Chief, NSS.

A oomplete analysis of the oiroumstances leading up to and resulting from the situation, together with recommenda-tions to prevent a recurrence, shall be prepared by the PORC.

This report shall be submitted to the Site Direotor, the Manager of "the Office of Nuolear Power, and the Chief, NSS.

Further reporting requirements of 10 CFR 50.36(o)(1) shall be met.

6.6 A.

Records and/or logs shall be kept in a manner conveni'ent for review as indicated below:

1.

All normal plant operation inoluding such items as power level, fuel exposure, and shutdowns.

2.

Principal maintenance activities.

3.

Reportable events.

Cheoks, inspeotions,

tests, and calibrations of components and systems, inoluding such diverse items as source leakage.

5.

Reviews of ohanges made to the procedures or equipment or reviews of tests and experiments to comply. with 10 CFR 50.59.

376

e" 6.

Radioaotive shipments.

7.

Test results, in units of mioroouries, for leak tests performed pursuant to Teohnioal Speoification 3.8.D.

8.

,Record of annual physioal inventory verifying aocountability of sources on record.

9.

Gaseous and liquid radioactive waste released to the environment.

10.

Offsite environmental monitoring surveys.

11.

Fuel inventories and transfers.

12.

Plant radiation and contamination surveys.

13.

Radiation exposures for all plant personnel.

14.

Updated, corrected, and as-built drawings of the plant.

15.

Reaotor coolant system in-service inspeotion.

16.

NSS reports of results of reviews and of cognizance of audits.

17.

Design fatigue usage evaluation.

a.

Monitoring, recording, evaluating, and reporting requirements contained in 17.b, below will be met for various portions of the reactor ooolant pressure boundary (RCPB) for which detailed fatigue usage evaluation per the ASME Boiler and Pressure Vessel Code Seotion IIIwas performed1 for the conditions defined in the design speoification.

In this.,

1See paragraph N-415.2, ASME Section III, 1965 Edition.

377

I I

6.0 ADMINISTRATIUE CONTROLS 6.8 Minimum Plant Staffing The minimum plant staffing for monitoring and conduct of operations is as follows.

1.

A licensed senior reactor operator shall be present at the site at all times when there is fuel in the reactor.

2.

A licensed reactor operator shall be in the control room whenever there is fuel in the reactor.

3.

A licensed senior reactor operator or SRO limited to fuel handling shall be in direct charge of a reactor refueling operation; i.e.,

able to devote full time to the refueling operation.

A health physics technician'shall be present at the facility at all times there is fuel in the reactor.

5.

Two licensed reactor operators shall be in the control room during any cold startups, while shuts,ing down the reactor, and during recovery from unit trip.

6.

Eit'her the plant manager or a plant superintendent shall have acquired the experience and training normally required for examination by the NRC for a Senior Reactor Operator~s

License, whether or not the examination is taken.

In a'ddition, either the operations supervisor or the assistant operaitons supervisor shall have an SRO license.

7.

A Shift Technical Advisor shall be present at the site at all times.

388

GENERAL HC~ACER O

.O5 aa 0 N 98m H 4 W 0 0 HANAGER OF POtZR AHD ENGINEERING OFFICE OF QJCLEAR PO'PEP.

~'VCLEAP SAFETY DIRECTOR OF QVALITY ASSVRANCE SITE DIRECTOR 5FNP SITE DIRECTOR

-SQNP SITE DIRECTOR VBNP SITE DIRECI'OR BLIP DIRECTOR OF

'VCLEAR SERVICES

Site Director Functional Reporting

Manager, Operations Quality Assurance Division of Quality Assurance Modifications Manager Site Services Manager Design Services Manager Quality Assurance Plant Manager Plant Compliance perations an Engineering uperintenden Maintenance uperintenden Operations Engineering Assistant Operations Group Supervisor Shift Crews Shift Engineer.

ASE UO AUO FIGURE 6.1-2 FACILITY ORGA'1IZATION

l t

ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION (TVA BFNP TS 201)

The proposed changes to Technical Specifications are required to correctly describe the new organizational structure of Tennessee Valley Authority.

Pages 317, 320, 326, 332-340, 346, 347, 358, 361 and 362 of units 1 and 2; pages 349, 352, 356, 362-370, 376, 377, 388, 391 and 392 of unit 3 revised to have the following nomenclature e changes:

Plant Superintendent changed to Plant Manager Assistant Plant Superintendent changed to Plant Superintendent Manager of Power changed to Manager of Office of Nuclear Power Nuclear Safety Review Board (NSRB) changed to Nuclear Safety Staff,(NSS)

Minor editorial changes and page number changes were also made.

Pages 353, 354, 356, 359, 362, 362A, and 394 of unit 3; pages 321, 322, 326, 329, 332 and 364 of units 1 and 2 - revised to delete references and interim organization of the fire recovery plan which has been completed.

Page 333 of units 1 and 2; page 363 of unit 3 remove section titled" Composition and Quorum and replace with sections titled Responsibility and Minimum Review.

Delete the section for meeting frequency.

These changes are related to the organizational change of the Nuclear Safety Review Board to the Nuclear Safety Staff.

Pages 337 and 346 of units 1 and 2; pages 367 and 376 of unit 3 delete requirements to distribute copies of PORC minutes and reportable events within TVA.

Pages 361-363 of units 1 and 2; pages 391-393 of unit 3 - revise the organizational charts to reflect the new TVA organizational structure.

The Table of Contents has been revised to reflect changes made to pages as a result of these organization specifications.

N 0

H ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS The proposed amendments would modify the technical specifications to:

(1)

Reflect the reorganization of TVA and the plant staff.

This includes changes to the organizational structure, changes in nomenclature, deletion of the technical specification requirement to send copies of the Plant Operational Review Committee meeting minutes and reportable events to the list of people within TVA.

Also to reflect that the Nuclear Safety Review Board was changed to the Nuclear Safety Staff (Units 1, 2, and 3).

(2)

Delete obsolete references to the fire recovery plan.

This includes deletion of the qualifications for the Safety Engineer and other interim organization of the fire recovery plan which has been completed (Units 1, 2, and 3).

P c

d C

n:

The Commission has provided examples of license changes which are likely to involve no significant hazards consideration (48 FR 14870).

One of the examples of actions likely to involve no significant hazards considei ations is: "(i) A purely administrative change to the technical specifications:

For

example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature.

Because the technical specification revisions discussed in (1) reflect, the revised organization of TVA,.it isan administrative change.

It is, therefore, encompassed by Commission example (i).

Change 2 is also encompassed by example (i). It would correct the technical specifications by deleting obsolete references to the fire recovery plan.

The fire recover y plan has been completed and the interim

.requirements are no longer needed.

4

~

~ ~

ENCLOSURE 1

PROPOSED TECHNICAL SPECIFICATION REVISIONS BRORlS FERRY NUCLEAR PLANT UNITS 1-, 2, AND 3 (TVA BFNP TS 201.)

0 4