ML19317F710

Amend 12 to License NPF-3,changing Tech Specs 6.1-6.12 to Reflect Changes in Administrative Organization of Util

ML19317F710
Person / Time
Site:	Davis Besse
Issue date:	08/18/1978
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML19317F707	List: ML19317F706 ML19317F710 ML19317F713 ML19317F716 ML19317F719
References
NUDOCS 8001230602
Download: ML19317F710 (23)

Text

..

O U%g t

f%

p

,a bg UNilf D STA TES y*

NUCLE An REGULATOnY COMMisslON

'To 'J *

E WAW46NGTON D C 2n%$

' "Nf

/

%,.....f a

Tiil TOLEUO LUISDN C0hPAfiY Af40

~-

THE CLEVELAND ELECTRIC ILLUMINATli4G C0!:PAM 00CKLT ilu. 50-346 DAVIS-BESSE NUCLEAR P0'nER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. NPF-3 1.

The Nuclear Regulatory Ccmission (the Comission) has found that:

A.

The issuance of this license amendment complies with the standards a'nd requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the license, as aniended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assuPonce (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) Lhat such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the ccamon 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 Conmission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the amended Facility Operating License No. NPF-3 is hereby amended by changing the Technical Specifications as indicated in the attachment to this license amendment.

8001230 h@

/

n

. 2.C.(3) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 12 are hereby incorporaud in the license.

Toledo Edison Company shall operate the facility in accordance with the Technical Speci ficatior s.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION D

G i

\\

/ h..

\\

,l l

/

)/

,\\Jah F. Stolz, Chief f Light Water Reactors Uranch No. I

, _ Oivision of Project Management

Attachment:

Changes to the Technical Specifications Date of Issuance: AUG 181978

r

+

c.

~

111

~

THE TOLEu0 EDISON COPPANY AND THE CLE'/ELAitD ELECTRIC ILLUMINAT!!iG C0hPAti7 00CKET hu. 50-346 DA'4IS-BESSE NUCLEAR POWER STATI0ft, UNIT NO.1 MEN 0HENT TO FACILITY CPERATING LICE *iSE Acenament ao. 12 License No. NPF-3 1.

The f uclear Relulatory Cocraission (the Commission) nas found that:

A.

The issuance of this license amendment complies with the standards and requirements of tna Atocic Energy Act of 1954, as amended (tne Act) and the Coassission's regulations set forth in 10 CFR Chaptar I;

B.

The facility will operate in conformity with the licensa, as amended, the provisions of tne Act, and the regulations of tiie Cccinission; C.

Tnere is reasonable assurance (1) that the activities authorized by this acendment can be conducted without endangering the health and safety of the public, and (ii) tnat sucn activities will De conducted in coupliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to tha comen defense and security or to the health and safety of the public; anc E.

The issuance of this a:aendment is in accordance with 10 CFk Fart 51 of the Comission's regulations and all appliccole requirecents have been satisfied.

2.

Accordingly, the ataended Facility Operating License No. iiPF-3 is hereby amended by changing the Tecnnical Specifications as indicated i

i in the attachraent to this license amendment.

OPPIC E P ouemams >

oate >

• vas.oove== mew,poinvine o m es sere.eae.eae NRC PORM 310 (b76) NROS 0240

r

?

-mn DJ 0

~

o v lb

- D '9' I j c

3 2.C.(3) Technical Specifications The Technical Specifications contained in Appendices A and 3, as retised througn knendment No.12 are hereby incorporated in the license. Toledo Edison Company shall operate the facility in accordance witn the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY C0teilSSION original swed by John F. Stolz, Chief Light Water Reactors Branch No. 1 Division of Project Managw.ent Attach =ent:

Chan';es to the Technical

$pecifications Date of Issuance: AUG 181978

/

LWR 1 LWR L

- 0Eth LWR A

.m..,

Eft 9d&n/ red LEn M M

JSto M. ~

3/I/78 8/} /78 3/h/78

_8{['[/78 oave,

NRC PORM 318 (9 74) NRCM 0240

_ _ j u. s. oovenaneswr >=.= vine omcas sere m

m Af f ACHt1LNT TO LICtriSt A!UiUr tiif fl0.12 i

FjyllLIT Y OPLHAilfiG LIClil5E f;U. i;PF-J COLKET fiU. 50-J46 Replace the foll0 wing pages of the Appendix "A" Technical Specificaticos with the enclosed peijes as indicated.

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

The Curresponding overleaf pages are also provided to naintJin document completeness.

Pages 6-2 6-3 6-6 i

m o1 6-9 D

D 6-11 b6S 6-19 F

'M[ Tgb OE A

6-13 D

6-14

._3 i"y 6-15 6-16 6-17 6-18 6-19 6-20

m.

6.0 ADMINISTRATIVE CONTRCt S 6.1 RESPONSIBILITY 6.1.1 The (Plant Superintendent) shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips, d.

An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.

e.

All CORE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsi-bilities during this operation.

f.

A Fire Brigade of at least 3 members shall be maintained onsite at all times. The Fire Brigade shall not include the minimum shif t crew shown in Table 6.2-1 or any personnel required for other essential functions during a fire emergency.

DAVIS-BESSE, UNIT 1 6-1 Amendment No. 9

s g

iJI

!:8 s;

gt:

=

-:I:

g gs:

fa.

i n

ij e g din,0)

E m-rr-oA 1.

~n I

I. E

? $

.i e

g; g

-r 3.

8 a

gg I

I.5 I

g og r

g!!

r a

It i-15 i

3:i i !l h

e!

15

!8 I

s!

- :r n

g.=

5

.:a sa e.

=

55

p; se.

tw!:

2r:1 li-

- El Eb:

- Ig

_t

I si 8*

~

[

yt l:s r

-: a IS, fil I

g c

i Y

lI!

_L 1).

f

!".I 55 is j5-i its aI 1

g

I

!5I isl is

.3 Eii

+!

j-I

a 3:

I

'I

__=

5.=

DAVIS-BESSE,' UNIT 1 6-2 Amendment No.12

F Ep fj

!.I:

I l 1,

1 ]

3 g-e.

gg.

g E

0 OP E5 D

EE~

gyk WW dsr O

~5 D

~' 9

' T

, P I

n F

k A

.l

-r ra g,6c v.

- s.J ~ JL 1.a "5

E.

E.

5 1=

a sl

.l lB I3 I.;=

ins.

8 i

g lg lg l

8 i

5 ii s.

-1 5I 15 "I

~

I

.I S:

=

wij

.I 1 5-El

i g!Ei BI iti g][8

=

\\

l l

a1

_ !tiil 31 a g*r si 5

1 1 I:

15 b

li

!i I

5I si it si E!

ij ji ij 35

~

a a

a 3

-3 g

a o

o 4

2 DAVIS-BESSE, UNIT 1 6-3 Amendment No.12

m i

TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #

LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL 1

1*

OL 2

1 Non-Licensed 2

1

• Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling supervising CORE ALTERATIONS.

1. Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

I I

l L

i I

l DAVIS-BESSE, UNIT 1 6-4

l

,m ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the (Radiation Protection Manager) who shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the (position title) and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Bridage shall be maintained under the direction of the Fire Marshall and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976.

6.5 REVIEW AND AUDIT 6.5.1 STATION REVIEW BOARD (SRB)

FUNCTION 6.5.1.1 The Station Review Board (SRB) shall function to advise the Station Superintendent on all matters related to nuclear safety.

OAV:S-BESSE, UNIT l 6-5 Amendment No.9

m ADMINISTRATIVE CONTROLS COMPOSITION 6.5.1.2 The Station Review Board sha-ll be composed of the:

Chaiman:

Assistant Station Superintendent i

Member:

Operations Engineer Member:

Technical Engineer Member:

Maintenance Engineer Member:

Lead Instrument and Control Engineer i

Member:

Nuclear and Perfonnance Engineer Member:

Chemist and Health Physicist Member.

Reliability Engineer Member:

Station Superintendent ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRB activities at any one time.

MEETING FREQUENCY 6.5.1.4 The SRB shall meet at least once per calendar month and as convened by the SRB Chairman or his designated altsrnate.

QUORUM 6.5.1.5 A quorum of the SRB shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The Station Review Board shall be respersible for:

a.

Review of 11 all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as detennined by the Station Superintendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear safety.

DAVIS-BESSE, UNIT 1 6 -6 Amendment No. 12

m m

n ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The Company Nuclear Review Boa d shall be composed of the:

Chairman:

Vice President, Facilities Development Member:

Vice President, Energy Supply Member:

General Superintendent, Power Engineering and Construction Member:

General Superintendent, Transmission and Substations Member:

Superintendent, Davis-Besse Station Member:

Superintendent, Production Services Member:

Nuclear Project Engineer, Power Engineering Member:

Nuclear Engineer, Power Engineering Member:

Director, Quality Assurance Member:

General Superintendent, Fossil Operations Member:

Others as deemed advisable by the CNRB Chairman

• ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the CNRB Chairman to serve on a temporary basis; however, no more than two alter-nates shall participate as voting members in CNRB activities at any one time.

"0NSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the CNRB Chairman to provide expert advice to the CNRB.

MEETING FREQUENCY 6.5.2.5 The CNRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.

QUORUM 6.5.2.6 A quorum of CNRB shall consist of the Chairman or his designated alternate and at least half of the appointed CNRB members I

cc their alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

• 0tners as deemed advisable by the CNRB chairman, who are appainted to the Company Nuclear Review Board shall have an academic degree in an Eng%eering or Physical Science Field; and in addition, shall nave a minimum of five years of technical experience, of which a minimum of three years shall be in one.or more of the areas specified in

.Spedification 6.5.2.1.

DAVIS-BESSE, UNIT 1 6-9 Amendment No.12

.m ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The Company Nuclear Review Board 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 actions did not constitute an unreviewed safety question.

b.

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

c.

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

d.

Propor?d changes in Technical Specifications or this Operating License.

e.

Violations of codes, regulations, orders, Technical Frucifications, license requirements, or of internal procedures or i~.tructions having nuclear safety significance.

f.

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

g.

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

i.

Reports and meetings minutes of the Station Review Board.

CAVIS-BESSE, UNIT 1 6-10

m ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of facility activities shall be perfomed under the cognizance of the CNRB. These audits shall encompass:

a.

The confomance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months, b.

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

c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.

The perfomance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months, e.

The Station Emergency Plan and im,lementing procedures at least once per 24 months.

f.

The Station Security Plan and implementing procedures at least once per 24 months.

g.

Any other area of facility operation considered appropriate by the CNRB.

h.

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

An independent fire protection and loss prevention program inspection and audit shall be perfomed at least once per 12 months utilizing either qualified offsite licensee per-sonnel or an outside fire protection firm.

j.

An inspection and audit of the fire protection and loss pre-vention program shall be perfomed by a qualified outside i

fire consulant at least once per 36 months.

j I

AUTHORITY 6.5.2.9 The Company Nuclear Review Board shall report to and advise the Executive Vice President, Operations on those areas of responsibility I

specified in Sections 6.5.2.7 and 6.5.2.8.

DAVIS-BESSE, UNIT 1 6-11 Amendment No.12

n

~

ADMINISTRATIVE CONTROLS RECORDS 6.5.2.10 Records of Company Nuclear Review Board activities shall be prepared, approved and distributed as indicated below:

a.

Minutes of'each CNRB meeting shall be prepared, approved and forwarded to the Executive Vice President, Operations 1

and CNRB members within 14 days following each meeting, 1

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Executive Vice l

President, Operations and CNRB members within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Executive Vice President, Operations and CNRB l

members and to the management positions responsible for the 4

areas audited within 30 days after completion of the audit.

6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a.

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

b.

Each 'REPORTAB;E OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the SRB and submitted to the CNRB.

DAVIS-BESSE, UNIT 1 6-12 Amendment No. 12

G l

I ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The facility shall be placed in at least HOT STANDBY within one hour.

b.

The Safety Limit violation shall be reported to the Commission, the Vice President, Energy Supply and to the CNRB within 24..

hou'rs.

l c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the SRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d.

The Safety Limit Violation Report shall be submitted to the-Commission, the CNRB and the Vice President, Energy Supply within 14 days of the violation.

6.8 PROCEDURES l

6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

l d.

Security Plan implementation.

e.

Emergency Plan implementation, f.

Fire Protection Program impleme %4 tion.

t 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed by the SRB and approved by the Station Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.

DAVIS-BESSE, UNIT l 6-13 Amdndment No. I,12 1

m s

/

ADMINISTRATIVE CONTROLS 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 Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the SRB and approved by the Station Superintendent within 14 days of implementation.'

6.9 REPORTING REOUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. 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 commitments shall be in-cluded in this report.

Startup reports shall be submitted within (1) 90 days following 6.9.1.3 completion of the startup test program, (2) 90 days following resumption or cocinencement of commerical power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the Star'.u; Report does not cover all three events (i.e., initial criticality, tenpletion of startup test program, and resumption or commencement of commercial Amendment No.[121 DAVIS-BESSEE, UNIT 1 6-14

.__=

1 m

i ADMINISTRATIVE CONTROLS power operation), supplementary reports shall be submitted at least every three months until all three events have been completed, i

1/

ANNUAL OPERATING REPORT 6.9.1.4 Annual reports covering the activities of the unit during the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their assogJated man rem exposure according to work and job functions,-

e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLP, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generation tube inservice inspections (Specification 4.5.5.b).

MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, with a copy to the Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.

1/

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

2/

This tabulation supplements the recuirements of 120.407 of 10 CFR Part 20.

DAVIS-BESSE, UNIT 1 6-15 AmendmentNo.I,121

m s

ADMINISTRATIVE CONTROLS REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his d.esignate no later than the first working day following the event, with a written followup report witcin two weeks. The written followup report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supple-mented, as needed, by addidonal narrative material to provide complete explanation of the circumstances surrounding the event.

a.

Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function, b.

Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative th.n the least conservative aspect of the limiting condition for operation established in the technical speci fications.

c.

Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

d.

Reactivity anomalies involving disagreemant with the predicted value of reactivity balance under stst y state conditions during power operation greater than or equal to 1% ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN less conservative than.pecified in the technical specifica-tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% ak/k; or occurrence of any unplanned criticality.

DMIS-sESSE, UNIT 1 6-16 AmendmentNo.f,12l 1

m ADMINISTRATIVE CONTROLS Failure or malfunction of one or more components which prevents e.

or could prevent, by itself, the fulfillment of the functional requirements of syste3(s) used to cope with accidents analyzed in the SAR.

f.

Personnel erroe or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional require-ments of systems required to cope with accidents analyzed in the SAR.

g.

Conditions arising from atural or man-made events that, as a direct result of the event require plant shutdown, operation of safety systems, or other protective measures required by technical specifications.

h.

Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reacter operation in a manner less conservative than assumed in the analyses.

i.

Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safe:y analysis report or technical specifica-tions bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor-rective measures to prevent the existence or development of an unsafe condition.

THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of 1

occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.

Infomation 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.

a.

Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not arevent the fulfillment of the functional requirements of affeded systems.

DAVIS-BESSE, UNIT 1 6 k7

,:mendment No

,12 l

r\\

n 9

ADMINTSTRATIVE CONTROLS b.

Conditions leading to operation in a degraded mode pennitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.

c.

Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

d.

Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the ap-plicable reference specification:

a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

b.

Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

c.

Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.4.

d.

Seismic event analysh, Specification 4.3.3.3.2.

e.

Fire Detection Instrumentation, Specification 3.3.3.8.

f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

6.10 dECORD RETENTION 6.10.1 The following records shall be retained for.t least five years:

a.

Reco ds and logs of facility operation covering time interval at each power level.

b.

Records and logs of principal maintenance activities, inspections, repa' and replacement of principal items of equipment related to nuclear safety, c.

ALL REPORTABLE OCCURRENCES submitted to the Commission.

d.

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

DAVIS-BESSE, UNIT 1 6-18 Amenchent No. pl2 l

m ADMINISTRATIVE CONTROLS e.

Records of changes made to Operating Procedures.

f.

Records of radioactive shipments.

g.

Records of sealed source and fission detector leak tests and results, b.

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

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a.

Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c.

Records of radia'. ion exposure for all individuals entering radiation control areas.

d.

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

e.

Records of transient of operational cycles for those facility compontats identified in Table 5.7-1.

f.

Records of reactor tests and experiments.

g.

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

h.

Records of in-service inspections performed pursuant to these Technical Specifications, i.

Records of Quality Assurance activities required by the QA Manual.

j.

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

k.

Records of meetings of the SRB and the CNRB.

DAVIS BESSE, UNIT 1 6-19 Amendment No.

12 l

I 3

ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protectien shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or "alam signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit *,

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 which continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated 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 knowl-i edgeable of them, c.

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

This individual shall be responsible for providing positive control over the activities within the area and shall perfom periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Pennit.

G.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.

In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Foreman on duty and/or the Health Physicist.

• Health Physics personnel shall be exempt from the RWP issuance require-ment during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

DAVIS-BESSE, UNIT 1 6-20 AmendmentNo.)l;12 l

_..