ML20128K634

Proposed Revs to Tech Specs,Changing Definition of Reportable Events & Changing Reporting Requirements in Response to Revs to 10CFR50.72 & 73 Re Immediate Notification Requirements

ML20128K634
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	07/31/1985
From:	CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
Shared Package
ML20128K625	List: B11584, Application for Amends to Licenses DPR-61,DPR-21 & DPR-65, Changing Tech Specs Re Reportable Events & Reporting Requirements in Response to Revs to 10CFR50.72 & 73 & Generic Ltr 83-43.Proposed Tech Spec Revs Encl ML20128K634
References
GL-83-43, TAC-55723, NUDOCS 8507240188
Download: ML20128K634 (57)

Text

,. _.

,q_l Docket No. 50-213 Proposed Revisions to Technical Specifications Haddam Neck Plant b

July,1985 8507240188 850709

~

PDR ADOCK 05000213 P

PDR-

r

,c INDEX l

.n.$..

?.

I

~

~

l

. DEFINITIONS l

l

.~

l SECTI0N 1.0 DEFINITIONS PAGE

~

1.1 Defined Terms...........................................

1-1 1.2 T he rmal P owe r...........................................

1-1

~

1.3 Rated Thermal Power................s....................

1-1 l

1.4 Opera ti o nal Mod e........................................

1-1 1-1 1.5 1.6

. Operabl e - Ope ra bil i ty..................................

1-1 1.7 Esportable Event.........................................

1-2 l

s

-1.8 Contai nment Inte gri ty....................................

1-2 1.9 Channel Cal i brati on....................................

1-2 1.10 C ha n n el C he c k...........................................

1-2 1.11 Channel Functi onal T est.................................

1-3 f..--

1.12 Co re Al t e ra ti o n.........................................

13-

+

i 1.13 Shutdown Margin..........................................

1-3 i

1.14 I denti fi ed Lea ka g e.......................................

1-3 l

1.15 Uni d enti fi ed Lea ka ge...

1-3 1.16 Pressure Boundary Leakage................................

1-4 l

l 1.17 Co ntrol l e d L e a ka g e.......................................

1-4 1.18 Quadrant Power Tilt Ratio..................'.............

1.

1.19 1-4 1.20 1 -4 l

.,.23 rrequency Nota: ion.......................................

, -4 1.22 1-5 1.23 1-5

(

)

1.24 Flux Difference................................[.........

1-5 1.25 Low Power P hys i c s Te s ts..................................

1-5 i

.Tabl e 1.1 Opera ti ona l Modes................................

1-6 l

Table 1. 2 Frequency Notation............................

1-7

'i INDEX

(,

1 ADMINISTRATIVE CONTROLS SECTION 6.0 ADMINISTRATIVE CONTROLS PAGE 6.5.2.4 Con s u l t an ts........................

6-9 6.5.2.5 Meeting Frequency....................

6-9 6.5.2. 6 Ouorum 6-9 6.5.2.7

' Review 6-10 6.5.2.8 Audits 6-11 Authority........................

6-11 6.5.2.9 6.5.2.10 Records.

6-12

-6.5.2.11 Qualifications 6-12

('7~

6.6 REPOP. TABLE EVENT ACTION 6-13

.s-6.7 SAFETY LIMIT VIOLATION....................

6-13 6.8 PROCEDURES 6-13 i

l REPORTING REOUIREMENTS I

6.9 l

6.S.1 ROUTINE REPORTS...................... 6-15

'.9.2L

.5PECIAL REPORTS....

6-18 6

6.10 RECORD RETENTION...'.

I.

6-18 I

6.11 RADI ATION PROTECTION PROGRAM 6-20

..,...........-.4 6.12 RESPIRATORY PROTECTION PROGRAM (DELETED) to 6.12 HIGH RADIATION AREA...................... 6-20 E.14 ENVIRONMENTAL DUALIFICATION -...

6-21 y

o i.'

e (O,

INDEX

\\

ADMINISTRATIVE CONTROLS SECTION 6.0 ADMINISTRATIVE CONTROLS PAGE 115 SYSTEMS INTEGRITY.....................

6-21 6.16 IODINE MONITORING -....................

6-21 e

C,.'.

- L I,

I 9

G I

S

\\'

h *~

l e

=

Vi L

3.'

N DEFINITIDMS i

REPORTABLE EVENT 1.7 A Reportable Event shall be any of those conditions specified in Section 50.73 to 10 CFR Part-50.

CONTAINMENT INTEGRITY i.B CONTAINMENT INTEGRITY shall exist when:

1.8.1 The containment automatic isolation valve system is OPERABLE.

~

1.8.2. All penetrations required to be closed during accident conditions are either:

a.

Capable of being closed by OPERABLE containment automatic-isolation valves, or

~

y l

b.

Closed by manual valves, blind flances, or. deactivated

! r^^)

~

\\

automatic valves secured and locked in their closed

..y/....

a positions,

1.8.3 All equipment, hatches are closed and sealed, and

~

~

1.8.4 Each door. in each air lock is closed and sealed except when l

~

the airliock-is being used for normal transit entry and exit

[

through the containment, then at least one air lock door shall be closed and sealed.

~

' CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shat 1 be the adjustment of thatynel output such l

that it responos, with. acceptable range and accuracy, to known va:1ues.

l cf the parameter which the channel ineasures.

Calibration shall. encompass.

the entire channel, including equipment. actuation, alarm, or trip.

CHANNEL CHECX 1.10 A CHANNEL IHECK shat 1 be the curlitative assessment of char.nel behavior duripp operation by oDservation. This metermination. shat 1: -

include, wnere possible, comparison of the enannel indication with other indications derived from inoependent instrument channels i.f(

)!

measuring the same. parameter-.

s l

e

.4 12 y

,...Te

,e

~

b.22'TIRI TRDTI C I U N

• Applicability

.L}

This specification applies to the operational status of the plant fire' protection and detection systems.

Obiec:1ve To ensure the availability of the fire protection and detectica systems.

Specification A.

Tire Suncression Vater Svstems

.A.1 The Tire Suppression Water System shall be operable during all modas of operation with:

a)

Two high pressure fire pumps, each vith a capacity of 2500 gym, with their discharge-aligned to the fire suppression header.

b)

Autor.atic initiation logic for each fire pump.

A.2 Trez and af ter the date that one fire pump is determined to be inoperable, restore the pump :o operable status vithin'7 days or prepare and submit a-("'-)

Repert to the Commission pursuan to Specification 6.6.1.

l

.u

., r..-

l A.3 Trom and af ter the time tha: the entire Tire S'uppression Water Sys sm is dete eined to Inoperable virh the-plan:

in any operating sode:

a)

Vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> establish a backup Tire Suppression Water Sys c.,.and prepare and sub=i: a Report pursuan: to Specification 6.6.1.

b)

The. plant shall be placed in at least Hot 3:andby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the-f ellowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l 1

I

(.

s 9

3-41

~,

,,,,e

3.

Carbon Dioxid'+ Syntems Systems shall be Oper ble with th2 3.1 The fellowing CO2 indicated, connected sinimum number of bottles.of CO2 and available f or service and having at least 90-(--)-

1m the area is required to be Operable:

of full charge weight, whenever the protected equipment i

a)

Cable Yault (18) b)

Primary Auxilia y Building Charcoal 711ters (8)

-3.2 from and af ter the time a CO2 system listed in 3.1 1s. determined to be' inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for the unprotected equipment.

and/or area. *

~3.3 ; Restore the system to Operable status within 14 days

' or prepare and submit a Report to the Commission pursuant to Specification 6.6.1 C.

Malot 1301 System The 11alon 1301 System for the switchgear room shall C.1 be operable with at least (7) lialen bottles - connected -

l and available f or service and each bottle shall be-

' ' )

at least $ of full charge weight.

' C.2 Tron and af te-the time the lialen system listed in C.1 is deterr.ined to be inoperable within one hour establish a continuous fire varch with backup fire suppression equipment ior the unprotected equipment and/or area.

C.3, Restore the system to operable status within 14 days or prepare-and submit a Report to the Commission pursuant to Specification 6.6.1.

j.,

' 3.

Tire Water Statiens The Tire Water Stations 11sted in inble 3.12-1 shan t.1 be Operable.

e 4

,9 I

,6Y %

g

, f

-y

D.2 From and cf tcr the time any cf the 71r's Watcr'. Stations a-

.H.

listed 'in Tchla 3.22-1 c.ra datermined to be Anoper:bla.-

vithin on2 hour T uta an additional cquivalent capacity hose to-the unprotected area from an operable fire C

water station or establiah a fire patrol to inspect the unprotected area at intervals of at least once sach hour.

)

I.

' Tire Deteerion Systems I.1 The minimum number of detectors for each fire

-detection zone shown in Table 3.22-2 shall be OPERA 3LI.

I.2 AC* ION Whenever the~ number of OPERA 3LI detectors is less than the minimum number OPERABLI requirement of Table 3.22-2:

J a.

Within I hour establish a fire watch pa:rol to inspect the zone (s) with the inoperable instrument (s) a: least once per hour, unless the instrument (s) ts located inside the containment, then inspect the containment at least once per B hours or (monitor - -

~

the containment air temperature at least once Ter '

hour at the locations reierenced by Specification 4.4, Containment Testing)..

b.

Restore the inoperable instrument (s) to OPERABLE

{~~S status within 14 days, or, prepare and submit a d

Report to the Commission pursuant to Specification

~W 6.6.1

~

7.

?enetra:1cn Tire ha--ters T.1 Tsenetration fire barriers -(including cable penetration barriers, fire doors and fire da=pers) tha: prote :

saf e y related areas shc11 be functional.

7.2 Trom.and.af ter the. :1me tha: -it is deter =1med that a penetration fire barrier is me dunc:1onal; (a) the

. areas shall be monitored.by operable fire detectors -

and within one (1) hour a. fire vecch patrol shall 'be established to inspect the 4rea of at least once Per

~

hour or (b).a continuous fire va:ch shall be established on at least one side of the affacted penetration within g,one (1) hour.

• J.

4 6

't 0-O 3-43 r

.g

c I*

~

C.2 From and citer the time any of the tyrsy and/or cprinkler systems listed in C.1 la determined to be Anoperable, within one hour,. establish a continuous fire watch with backup f. ire suppression for those areas starred (*) in

{.h G.1; for other areas, establish a fire patrol to inspect the applicable unprotected area at intervals of at least once each hour.

C.3 Restore the inoperable system to operable status within

'14 days or prepare and submit a Report to the Commission pursuant to Specification 6.6.1.

Basis A.

Tire beteerion and Suerression Systems m

Tire Sue ression Svste=s The operability of the fire suppression sys: ems ensuras that gN adequate. fire suppression capabilt y 1s available to confine

! O,- - ) -

and extinguish fires occurring in any portion of the facility where safety related squipmen: is located Tne. fire suppression systa= consists of the vater. systems, spray and/or sprinklers, CO2 Sys:e=s, F.alon' 1301 Sys: ems, fire hose l

',[

s:a:1ons and hydranta.

Tne capabill:y of the fire suppression systems is adequate to sini=1ce potential damage to saf ety related equipment and -is 41 major element in the f ac111:y fire protet:1on progrs=.

In the even: tha: a portion of the Tire ~ Suppression System becomes inoperabit 4lternate backup fire fighting equi; ment or a periodic fire va:ch pa: ol is required to be. established in the associa:ed arsa until the inoperable equipmen:~can be res:ored :o service.

In the even: tha: the fire suppression va:er system becomes inoperable,1==nediate corree:1ve measures mus: be taken -

since this system provides the major fire suppression capabill:y of the plant.

Ine requirement for a twenty-four hour report to the Coss:.1ssion Trevices for promp:. evaluation of the acceptability of.he corree:1ve. measures to provide adequate fire suppression capability for the continued

~'

protec:1on of :he nuclear plant.

)

t

r k

ADMINISTRATIVE C0flTROLS

.\\

REV1EW 6.5.2.7 The NRB shall review:

a. 7he 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, 30 CFR.

, c.

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

d.

Proposed changes in-Technical Specifications or licenses.

Violatfons of applicable' statutes, codes, ' regulations, orders, e.

~

Technical Specifications license recuirements,' or of internal

(('

procedures or instructions having nucle'ar safety significance..

f.

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

,. safety.

2 All R'eportable Events.

'... h..Jndications of a significant unanticipated deficiency, affecting nuclear safety, in some aspect of cesign or operation of safety related structures, systems or comoonen.s 1.

Reports and meeting minutes of the PORC e

f (c

]

6-10

e' e

A!Pfr.TISTRA*TVI CD'f?RC" 3 6.6 REPORTABLE EVENT ACTION

'l 6.6.1 The following actions shall be taken for Reportable Events:

The Commission shall be notified and/or a report submitted a.

pursuant to the requirements of Section 50.73 or 10 CFR Part 50, and

~

b.

Each Reportable Event s' hall be reviewed by the PORC arid

• the results of this review shall be submitted to the NRB and the Vice President Nuclear Operations.

~

6.7 SA? TTY 1!MIT VIO1ATION 6.*7.1 '

The following actions shall be taken in the event a Safety Lini: is violated.

The unit shall be placed in at least BOT STANDBY vithin one hour a.

b.

The NRC Operations Center shall be notified by telephone as soon as'possible and in all cases within one hour. The'Vice Presiden:

huclear Operations and the NRE shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

A Safe:y limit Viola: ion %epor ahall be prepared. The c.

repor: shall be reviewed by :he 70R0. This tape-:

U shall describe (1) applicable circumstances preceding I

the violation, (2) effects of the viola:1on upon

~

f acill:y componen:s, systems er a: rue:ures, and (3) corrective ac:1on taken to preven: Tecurrence.

d.-

The Saf ety lini: Tiela:1on %eper: shab be subst::ed to the Cc~ission, the NRE~and :he Tice President-Nuclear Dpera:1ons within 34 days of the viola:1on.

6.8

?R000DI?.!S l

6.2.2 Vritten procedures,and.ad d-istra: Ave pc11ctes shall be

-es:ablished, implemented and sai. tained that see: ar -exceed n

the Tequiremen:s and Tecosamendations of See:1on 3.2.and 3.3 of ANS2 NIE.7-Ic76 and.Appesdix *'A".of I'5A!O Regulatory Guide.1.33 <xcept as Trevided in 6.*8.'2 and f.E.3 'below. -

l Trocedures.shall be.estab21shed,and maintained for amplementarioc' -

of the 7ac111:y Tire Trotec:1on Trogram.

6. $.2 7.ach procedure and administrative policy of 6.1 above.

and changes there:c, shall be reviewed by :he ?OR and approved by the Sta:1on.Superintenden: yrier te amplements:1on and periodically as. set f orth an sach document.

~

6-13 n

- d....

6.9 REPORTINC REOUIREMENTS C.

in addition to th'e applicable reporting requirements of Title 10 Code of yederal Regulations, the following identified reports shall. be submitted to the Regional Administrator of the appropriate regional office unless otherwise noted.

l 6.9.1 Routine Reports a.

Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manuf actured by a different fuel supplier, and (4) modifications that may have significantly

• * ^ * '

altered the nuclear, thermal, or hydraulic performance of the plant.

The report shall address each of the tests identified in the TSAR and shall in general 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 specifications.

Any corrective actions that were required to obtain antisfactory operation shall be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

Startup reports shall. be. submitted within (1) 90 days f ollowing completion of the startup'

-r test, program, (2) 90 days f ollowing. resumption

,,,..or commencement of commerciel*' power operation,

.' or.(3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.t., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until al1~three events have been completed.

b.

Steam Generator Tube Insnection - The complete results of tne steam generator tube inservice inspection shall be reported within ninety days after completion of the inspection.

This report 1

shall include:

1).

number and extent of tubes inspected.

2).

location and percent of wall thickness

(,

penetration for each indication of an

~

i

+

imperf ection.

g t

6-15 a

l -:<,,

1 1

1

.... 6 o

f-t-,

1'

3) Identification of tubes plugged.

c.

Decupational Exposure Report The annual report shall be submitted prior to March 2-of each year and shall cover the previous calendar year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

This annual report shall include a tabulation on an annual basis of the mumber of station, utility, and other personnel (including contractors) receiving exposures greater ~than 100 arem/yr. and their associated man-rem -ex job functions.,i/e.g.posure according to work and

, reactor operations and surveillance; inservace inspection, Tourine maintenance, special maintenance (describe maintenance),

waste processing and refueling. The dose assignment -

to various duty f unctions may be estimated based on pocket dosimeter, TLD, or film badge measurements. - -

Small exposures totalling less than 201 of the individual total dose need not be accounted -f or.

In the aggregate, at least 801 of the total whole

/"-.

body dose received from sxternal sources shall be I

s assigned to specific major work functions.

d.

Monthlv Doeraring 'Renert - Routine reports of operating I

statistics and shutdown experience.shall be-submitted en a senthly basis to the Director, Office of hanagement infornation.and Program Control,. A S. Nuclear Regulatory Com=ission, Washington, T. C.

20555, with a copy to the appropriate Regional Office, to be postmarked no later than the fifteenth of.each month Jollowing the calendar month covered by thp repert.

The monthly Teport shall include a na rative su= mary of operating experience during the repor: period

~

Telating to saf e operation of the f acility, including safety-related maintenance.

1eports re9uired as per 10 CTR 30.59b.

s.

e O

9 e

f i

6-16

r

_T

~'

ADMINISTRATIVE C0hTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of 2nspection I, Inforcement Regional Office within the time period specified f or each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

Inservice Inspection results, specifications (4.10) 'and (4.12).

a.

b.

Primary Containment Leak Rate Results, Specification (4.4).

Reactor Vessel Material Surveillance Specimen Examination, c.

Specification (4.10).

.. d. 3:can Generator Tube Report Tollowing each inservice inspection of steam generator rubes, the number of tubes plugged in each steam generator shall be reported to the Commission vi:hin 2.5 days.

(~

T,']

6.20 P2 CORD 72TENTION a i'I 6.10.1 The following records shall be re:ained for a: leas: five years:

Records and logs of facility operation covering time interval a.

at each power level.

b.

Records and logs of principal maintenance activities, inspec: ions, repair-and replacemen of principal,1: ems of equipmer. related :o nuclear safery.

c.

All: Reportable Events.

4.

Records of surveillance.activi:1es, inspections and calibrations required by :hese Technical Specifications.

.6 am 4

6-18

e i-

~

AM1HISTCT1yr CC"TROLS i

l-e.

Records of rea::or tests and experiments.

' f.

Records of changes made to Operating Pro:edures.

1 s.

Ite:ords of radion:tive shipments.

h.

Records of setied source itak tests and resuits.

1.

Re:ords of annual physical inventory of all source material of

\\

record.

I j.

Radiation and conta=ination surveys.

)

6.10.2 The folloving ree:rds shall be retained for the duration of :.he Fa:ility Operating license:

l l

Re:ctd and drawing changes refie::ing fa:ility design modifi-a.

. cations made to systams and ecui::en: ces:ribed in :ne Fa:ility-Desc-iption and Safety Analysis Report.

t.

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

\\

(

Records of fa:ility radi.ation and conta=ination su vers.

c.

.)

~d.

Re:ords of radiation exposure for all individuals entering

~

l radiation control areas.

[

i e.

~ Records of Saseous and liquid radiot::ive material released to ;.he f

environs.

t f

~ Records cf transient or sperational :y:les for.those fa:il.ity

' components designed for a. limited num:,er of transients or cy:les, l

3 Re:ords of trainin; and qualifi:ation for current memoers of the

_ plant staff.

h.

T.e:'or s of in-service inspec: ions perfo :ed

• pursuant to these

• ie:nnical Spe:ifications.

L

-1.

Re:ords of'Outlity Assuran:e h:tivities required by the'QA hanua).

t J.

Re:ords of reviews 6erfo=med for :banges made to pro:eiures er t:vi = ens or reviews of test.s and L:periments pursuan: To l

10 CF:t 50.59.

1.

Re:ords of meetings of the PDT.* and the xty;.

l 1.

%e:erds is: !=-ire =me=:a1 Dualific::i==

.ich are covered.:nder the A

i i

yrov1:1cas of paraprash 6.14.

6-19

.d.

('

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

6.12 SUPERSEDED BY 10 CFR 20.103(c) AND (f) ON DF.CEMBER 28, 1977 6.13 HIGH RADIATION AREA c

6.13.1

~

In lieu of the " control device" or " alar = signal" required by paragraph 20.203(c)(2),

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 en-trance thereto shall be controlled by reouiring issuance of a Radiation Exposure Authorization *.

An individual' or group of -individuals permitted to enter such areas shall be provided with one or more of the following:

a.

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

('..

b.

A radiation monitoring device which continuously integrates n] ~

the radiation oose rate in the area and ala'rms wnen a preset integrated cose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area have been established and personnel have been made knowledgeable of them.

.s c.

A health physics cualified individual (i.e. cualified in radiation protection procecures) with a radiation oose rate monhering cevice wne is responsible for providine poshive control over the activities within :ne area and wne will perform periodi: radiation surveillance at the frecuency see:ified in tne REA. The surveillance frequency will be established by tne Health Physics Supervisor.

The ' tieve ' rocecure shall also. apply to each high radiation area in which the a

p intensity of radiation is creater than _1000 inrem/hr. r In addition, locked doors shall be provided to prevent unautnor.12ed envy-into such areas and the keys shall be maintained unoer tne noministrative control of the shift supervi'sor on outy.

• Health Physics personnel shall be exempt from the REA issuance recuirement during the performance of their assigned radiation trote: tion outies, providing tney are -following plant radiation erote: tion procedures for entry into high radiation areas.

s

)

6-20 b

e 4

.*,.p

P ADMINISTRATIVE CONTROLS t,

e 6.14 ENVIRONMENTAL 00ALIFICATION A.

By no later than June 30, 1982.all safety-related electrical couipment in the f acility shall be -Qualified in accordance with the provisions of

- ~

Division of Operating Reactors " Guidelines for Evaluating Environmental Dualification of Class IE Electrical Ecutoment in Operating Reactors" (DDR Guicelines); or, NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Eguipment", Decemoer 197S.

Copies of these occuments 'are attached to Orcer for Modification of License DPR-61 dated' October 24, 1980.

E.

By no later than December 1, 1980, complete and auditible records must be ava'ilable and maintained at a central location which describe the environmental cualification method used for all safety-related electri-cal ecuipment in sufficient detail to occument the oepree of compliance. - - - -

with tne DDR Guidelines or NUREG-0588. Thereafter, sucn records should be uodated and maintained current as equipment is replaced, further-testec, or otherwise further qualified.

6.15 SYSTEMS INTEGRITY The licensee shall. implement a program to reduce ' leakage from systems outside containment that wc;1d or could connin highly radioactive fluids curing a f

' i g) shall incluoe the following:

. serious transient or accioent to as low as practical levels. This program t

1.

Provisions establishing preventive maintenance and periodic visual inspection requirements,' and

~,,.,

2... Integrated leak test reacirements* for each system at a frequency Tiot-to exceed refueling cycle intervals.

6.16 _10 DINE MONITORING Tne licensee shall imolement a program which will ensure the tapability to accurately dete mine the aireorne iodine concen: ration in vital areas unoer l

accioent conditions. "This program shall incluoe.ne following:

1.

Training of personnel, 2.

Procedures for monitoring, and -

3.

Provisions for: maintenance of sampling and analysis ecuipment.

l e

e

.g i'

6-21 e

O

vf..

Docket No. 50-245-Proposed Revisions to Technical Specifications Millstone Nuclear Power Station, Unit No.1 July,1985 j

i

3

.e 3 -

6 s

i t

I Page No.

6.4 Training........................................................................

6.5 Revi ew a nd Audi t...........................

6-5 6.6 Reportable Event Action.......................................................

6-3 67 sarety Limit Violation..........................

6.......

4...................

6-15 I

6.8 Procedures...................;.................................................

6-15 6.9

...e.............................

6-16 Reporting Requirements 6.10 Record Retention.....a.6.............................................

6-17 6.11 Radiation Protection Pro 6-20 6.12 Hi gh Ra di a t i on A rea.... gram.................................. 4...............

6-21 6.13 Env i r onmen ta l Qu a li fica ti on...................... +...... a.....'..................

6-21 6.111 systems Integrity.:.....................

6-23 6.15 Iodine Monitoring..................:.....

.............a....e..................

6-23 6-23 i

ly Hillstone Unit 1 L

G 5

4

=,.

f

'2.

Trin System A trip system means an arrang'ement pf instrument channel trip signals and auxiliary equipm to initiate action to accomplish.s protective action.

channel trip signals related to one or more plant parameter.s in order to initiate trip system funct i,

tripping of two trip systems. initiation of protective-function may require the tripping of a single tr 3

Protective Action

(

An action initiated by.the protection system i+en a limit is exceeded.

channel or system level.

A protective action can be at a 4.

Protective Function A system protective action which results.from the protective action of the channels monitoring plant condition.

P.

Rated' Neutron flux e

I Rated neutron flux is the neutron flux that corresponds to a steady-state thermal power level of 2011 megawatts.

Q.

Rated 1hermal Power Rated thermal power means a steady state thermal power level of 2011 megawatts, R.

(left intentionally blank)

.t Hi11 stone tlnIt No. 1 4'4,

~'

a

't

-9

S.

• Reactor Power Operation l

Reactor power operation is any operation with the mode switch in the "Startup/ Hot Standby" or "Run" position with the reactor critical and above 1% rated thermal power.

1.

Startup/liot Standby Mode in this mode the reactor protection scram trips, initiated by condenser low vacuum and main steamline isolation valve -

closure, are bypassed when reactor pressure is less than 600 psig; the low presstre main steamline isolation valve closure trip is bypassed, the reactor protection system is energized with IRM neutron monitoring system trips and control rod withdrawal interlocks in service.

2.

Run Mode In this mode the reactor protection system is energized with APRM protection and RBM interlocks in service.

T.'

Reactor Vessel Pressure l

Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steain space detector.

U.

Refueling Outage 1

Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the plant subsequent to that refueling. For the purpose of designating frequency of testing and surveillance, a refueling outage shall mean a regularly scheduled refueling outage; however, where such outages occur within 8 months of the completion of the previous refueing outage, the required surveillance and testing need not be performed tsitil the next regularly scheduled outage.

J V.

Reportable Event A Reportable Event shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

c l

l-5 Hillstone Unit No. 1 l

p' p-

~

=

~

v

.?

LIMITING-CONDIT10N FOR OPERATION SilRVEILLANCE REQUIREMENT

{ E.

Reactivl'tyAnomaliesI

~

E.,

Reactivity Anomalies The reactivity erguivalent of the difference between the actual critical rod configuration During the startup test pr,ogram and startups and the expected configuration during power following refueling outages the critical rod configurations will be compared to the-operation shall not exceed 11 Ak, if this i

Ifmit'is exceeded, the reactor wl11 he shutdown expected configurations at selected operating conditions. These comparisons will be used until the cause hat been detennined and corrective actions have bepn taken if such as bpse data for reactivity monitoring during

~

subsequent power operation throughout the actions are appropriate.

~

~

fuel cycle 4 At specific power operating-conditions the critical rod configuration

~

Will be com, pared to the configuration expected T.

If Specification 3.3 A through n above are not based upon appropriately corrected past data.

met & normal orderly shutdown shall he This' comparison will be made at least every initteled and the reactor shall be in the cold equivalent full power month, shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Allowable combinations of thermal power and d~

• G total core flow shall be restricted to Curve I shown in figure 3.11.,

1.

~

i 4

N

/'

3/4 3-6 I

. ' Hills' tone Unit No. I e

s t

I e

a

l

~

• l.

LlHlithG CONDITION FOR OPERATl0H SIQVEILL ANCE ret)UIREMENI

.o

' replacessent charges to be installed will be selected from the same batcl.

as those tested. Both systems shall be tested and inspected. Including each emplosion valve in the course I

i of two operating cycles.

'b.

Manually initiate each system, except

,t the explosion valve and pump solution I

in the recirculation path back to the storage tank.'

c.

Test that the setting of the system

)

- pressure relief valves is between 1350 and 1450 psig.

B.

Operation with inoperable Ca=aonents from and after the date that a redundant component is made or found to be Inoperable.

Specification 3.4.A shall be considered fulfilled, provided that:

1.

The component'Is returned to an operable condition within 7 days or 2.

A written report shall be submitted to l

the Nuclear Re2ulatory Commission when

-the maintenance to. restore. the component to an operable' condition will last longer than 7 days.

~

d Per errata sheet dtd 10-7-70' 3/4 4-2 Hillstone Unit No. 1 O

n i

y o

9

f I

i, llHillNG CONDITION FOR OPERATION.

r SURVElttANCE REQUIREMENTS 1

2.

With one pump and/or one water supply !noperable.

restore the inoperable 'equiriment to 'OPERAl:l E d.

At least once per 12 months by

{:

status within 7 days or, in lieu of any other cycilng each testable valve in

-l report required by Specification A.6.1, pre-the flow path through at 1 cast 4

4 Y

pare and submit a Special Report to the

.one complete cycle, of full travel. '

Commission pursuaht to Specification 6.9.2 J]

within the next 30 days outlining the plans

'At least'on,c,e pe,r 18 months by per-e.

and procedures to be used to provide for the 7

forming a system functional test.

loss of tcdundancy in this system, which includes simulated auto.3atic actuation of the system through its' 3.

With the fire suppression water system other-operating sequence, and

,{

wise Inoperable:

i, la Verifying that each pomp j

Estabitsh a backup fire suppression water, develops at least 1800 gpm at a.

j system within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 3

4 a system head of 100 psig.

b.

}

Submit a Special Report in accordance with 2.

Cycilng each. valve in the floit Spec.ification 6.9.2; path that is not testable during.

plantLexceptvalve1-F-11)

By telephone Within 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br />,-

operal on through at least one '.

I, 1.

co*Plete cycle of full travel',~and 2.

Confirmed by telegraph, mallgram, or facsiraile transmission no later than 3

Verifying that each high pres-the first workirg day following the sure pump starts (sequentfally) y event, and to maintain the fire suppres-slonwatersystempressure>J5

'In writing kf th 14 days followl'ng the psig.

3.

q'

' event, on.tlining the action taken e the f.

At least once per 3 years by perform-

~

..causf of the Inoperability andcthe plans

.and schedule for rcstoring the system ing a flow test of the system in to OPERABLE slitus, accordance with Chapter 5. Section il of the Fire Protection Handbook,14th i

v.

F Edition, pubilshed tiy the National

'8 Fire Protection Association.

.i.

{

.s Hillstone tinit No. 1 f'

giu 3/4 12-2

~

'.I 44'

. pt '

-1

.. 3

.y 3

).4..M c.4

..a

{*

g

_y f

1.INITING CONDITION F04 OPERAff0N I

4 SURVEILt.ANctR$qutREMENTS.

f.

'. ~

3

).

k.

Spray and/or Sprinkler Systems B, spray and/or Sprinklar svetene a

[k 1.

The follouing spray and/oi sprinkler cystsime,

' 1.

Each of the spray /sprink1Jer systems in 3.12.8 located in.the follouing

• erable at all times when,arese shall be op-shall be demonstrated OPEP.Aal.Es

'},

equipment in the area

([;

it required to be operablet a.

At least once per.12 sionths by cycling each testable valve in the flow path through at -

f 4.

Diesel Ce' nerator Roda - inanually oper.sted least one complete. cycle of full travel.

o-ba Diesel Generator Day Tank' Room

.b.

/At least once per 18 months

• Ilydrogen Seal 011 )init' 1.

By performing a system functional test c.

which includes simulated automatic i

d; Cdi Tdtbine Building - manually operated actuation of the system, ands 1

I l

e.

• Condens4r Bay (a) Verifying that the automatie valves I

in the flow path actuate to their f.

. Turbine 1.ubrication -- 011 Room Deluge correct positions on a sl=ulated i

test signal, And s

,s Rood and Hachin4 khop-vet pips (b) Cycling each valve in the' flow path g.

Baller f +'{ '

• that is not testable durisig plant operation (except valve I-F-71) h.

. Bearing t.Ift Pump Anil Seal,011 through at least one complete cyclo Detraining Tank

- wet pipe-of full travel and f

I 1.

Reactor.Bulldink 14'-6E'levation - wit pipe 2.

By inspection of the spray head rs to i

verify their integrity. and 2.

With one or more of. the stove required spray And/or sprinkler systems inoperable, establish.

3.

By inspection of each noiale t'o' verify 6

e continuous fire watch with backup fire suppres-no blockage.

slon equipmerit for the unprotected mica (s) within I

1 hourt restore the system'to OPEF.ABl.E status within 14 days of6 in ileu'of Any other report re-

~

quired by specificat ion 6.6.1, prepare and sul,mit

[

a Special Report,to the Cossetsalon pursuant to

,]l 1[

Specification 6.9:2 within.the next '!O days out-l

'.rt

. '[*ll ]

' ' fI

• ** M.

i.N

!!ning~the ackfon taken6 the,cause of the inop-erability and the pland and schedule for reator-

'M'.

i jl -

i

.i,ing the systed to OPERANT.E sta'tue4

'3'

? M'

{,.

1 3/4 82-5 4'

L H i.i l sitone tini t No.' i

. ' '. ' ' * ' "T ' '

r.'. ' i i

1, (.

a

' ?' " y,, 7!s a rk L...u,. ; g p,,,

\\

m

i,

~

~

b

' O' Md9 i

'us

.1 LIMITIHC CONDITION FOR OPERATION

(!

t' 1.'.

SURVEILLANCE REQUIREHENTS

, 9.;

p

(

C'.' Carbon Dioxide 'and flalon 1301 Systems 1.rs i.

Y, C.

~

Carbon Dioxide and Italon 1301 Systems

.f 2

ci..

1.

The following high pressure CO 2 systesis shall 1.

Each of the high pressure CO l

l 2

be OPERABLE with the storage tanks' at least 90%

2 systems in 3.12.C.!

j shall be demonstrated OPERABLE:

of full charge weight whenever equipment in the

(-

high pressure CO i

2 Protected areas is required

-to be OPERABLE.

a.

At least once per s siontils by verifying CO 2

atorage tank weight.

4.

Cas Turbine Enc 1&sure r

Atleastonceperl[suathsby:

b.

2.

With one or more of the above required high' pres-j-.

t

8..

sure CO 1.

Verifying thk sFstem, inclisd1Ng 'aJsd6f ated l

2 systems inoperable. establish a contin-uous fire watch trith backup fire suppression equip-ventilation dampers, actuates automatically for the unptotected area (s) within I bour; upon receipt of a slaulated test signal and ment restore the system to OPERABI.E status within 14 manually through operator action, and days or, in lieu of dny other report required ffa :' <*

• W1

}.

by Specification 6.6.1, prepare and submit a 2.

Performance 'of.a visual inspection of'the S;*clat Report to the (;onesission pursuant to discharge nozzles to assure no blockage.

4 Specification 6.9.2 within the next 30 days out-

,. r,..,.

lining the actiod taken, the cause of the Inop-

<j etability and the plans and scigedule for restor-

)*

Ing the system to OPERABLE status.

2.

The Halon 1301 System referenced in 3.12.C.3 shall be demonstrated OPERABLE:

q\\.e s.. j' 3.

The' Halon 1301 System for th'e ' fire'pumMhduse

~

', g' shall be operable, with th'e bottles connbeted At least once per 6' months..-

the weight a.

a.

and available for service and the bottle at and pressure of the' refillable container shall

'f 95% of full charge weight.

be checked.

If the container shows a loss in 1

o

(.g' net weight of more than 5% or the pressure i

4.

From and after the time the fire pump house drops to 325 psig it shall be refilled or

~

E replacede Halon System is determined to be inoperable i

,(

within one hour establish ~a continuous fire b.

At least once per 18 months by:

watch with backup fire suppression eqisspoent for the unprotected equipment and/or area; 3

1, restore the system to OPERABLE status within 14 Verifying the system, including

• • • d ***d "*""U* d " d*N '***

days or, in lieu of any other report required i

9 "

• .. hy specification.656.1, prepare and submitt a of a simuisted test standt and Special Report to the Commoission pursuant to i. f.l Speciffention 6.9.2 within the next 30 days out -

.,3 e

g

,p,,,g,,,,

! y'.j,.

', lining the action taken, the cause of the inop-l

, f/

i etability and the plans and 5cheddle for restor-

.p g{

y ] ; g y g-gg.

1 ing the system to OPERABLE status.

i.);of the discharge nozzles to assure 3g g[_7 no blockage.

Hillstone Unit No.l1 t

'I

.,)

{.

i d'

l.IHtitHC CONDITION FOR OrknATION setmE RHNd t

P n

l

~

~1.

t.

fir,e_,tpetectloninstrumentstion.

E.

. Fire Detection instrumentation o

i f

1.

The minimes requited fire dettttien f*strumente Y

,1.

The fire' detection'in k ruments listed in

!~

tion for each fire detection mone shsinin in Table.

t Table 3.12.2 shall be desionstrated OPERABLE i' * ' *

{

.3.11 1 shall be OPERAtLE whenever'equipoent in at least once per 6 months be performance t

L@

that fire. detection some le requited to be of an INSTRUHENT FUNCTIONAL TEST with the OrtRABLt.

exception that the functional test may

[. :

~

With less then the nintiInum required nuder of the consist of injecting a simulated elects;,1 cal'

'I fit 4 detectise instrument (s) shown in Table.

sianet into the measurement channel rather-than the instrument.,Due to the inaccessability 9

3.12.2 OPERABLE 4 oft $afiredetectorslocatedinthecondenser

'i-

~'

gl.

~

i d.

Eithin i lieur istahtish 's watch.pstrel boy, 4 semple coneledng.of 1/3 of the detectors per channel will be kosted.during every refue!

!(.

to inspect;the sene(e) with the iner-

't outage. The sample test cycle will be comp!ated

,.erable jestrumeet(6) at ledet once per

! every third refueling outage...,

t 6.or, a.d IJ h'

o h

b.

diester 6 the inoperabl6 Igstemment(s) to 24 The non-supervleed circuits between the' above orERAsLE st&two kithis 14 days era in required detection instruments and the control j

lidia of anF ether report required by,

room shall be demonstrated OPERA 81.E at least i

l*

Specification'6.6',1, propers and sub,-

once per.31 days,'per approved procedures.

mit a spectat Report to ths commiselos' y

1

.... pursudet.se sp4cificelled 6.9.2 withim..

l the next 30 Jaye euttimins' the detted' takes, the eense of the inoperability

)c And the ptses sind schedele for rester--

)j lag kh4. instrument (s). to OPERASL5 T..

.' ~

statues G eil

{

j.

1.

l9 J

18 J.

4!

d.,:

U,D,.;

4

?

t i

~

,c 1

]

4

-.., s..

14 12-lp

,q.

'i

[*

)1 i

~

<.p'M Hillstone Unit No.-1

,r p

k'h J

b.

$....O*

.i

(~T f

't.tHITING CONDITION FOR OPERAT10H-StfRVEll.t.ANCE ILEqu!REHENTS I

l'.

Fenetration Fire Barriers F.

Fenetration Fire Barriers p.-

1.

All penetration fire barriers (includinr cable 1.

Penetration fire' barriers shall be verified

(

penetration fire hertiere, fire doors, and fire to be functionats dampers) Ohleh protect estety-related. areas shall 4

f, be functional whenever safety-related equipment s.

At least once per 18 montles by a visual 4

In the stes le required tci be operable, inspection.

B 2.

With one or more of flie abovi required J

b.

Prior to returning a penetration fire.

i penetration flire barriers non-functional.

barriet to functional st.1tus following I

within i hour establish a temporary fire t' pairs or maintenance by performance e

f barrier of equal effectiveness or estab-of a visual inspection er the affectrd

~g

• lish a continuous fire watch on at least penetration fire barrier (s).

one side of the affected penetration:

{

Restore the fire barrler(s) to functions!

~.

j status within.10 dayd nrg in lieu of any.

ether report -requited by Speelfiestion 6.6.1',

b[

prepare and submit a Specist Report to the

.Cossetssion pursuant to Specification 6.9.2

'I within the next 30 days outlining the action

. tsken, the cause of the fire barrier (s) being non-functiostal and the piens and schedule for

~

restoring the fire barrier (s) to functional

. Status.

'9 y

J.,s; 9

.):;

t:

• t ' :.

O's t

i

,j..'

1 I; 's 4

v..

a

,f. * -

s.

,3

.9*

0 e'

+

i :,

.Q 3

.N.

!*'.h,

n.

2 Hillstone Unit Ho, I p

y 30*

t 4

s

c ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman.

QUORUM 6.5.1.5 A quorum of the PORC shall consist of the Chairman or Vice Chairman or Station Superintendent and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

Review of 1) all procedures, except common site procedures, required a.

by Specification 6.8 and changes thereto, 2) any other proposed -

procedures or changes thereto as determined by the Unit Superintendent to affect nuclear safety.

b.

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

c.

Review of all proposed chdhges to Sections 1.0 - 5.0 of those

~

Technical Specifications.

d.

Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

Investigation of all violations of the Technical Specifications and e.

preparation and forwarding of a report covering evaluation and recommendations to prevent recurrent to the Vice President Nuclear ~ -

Operations and to the Chairman of the Nuclear Review Board, f.

Review of all REPORTABLE EVENTS.

~

L g.

Review of facility operations to detect potential safety hazards, i

i h.

Performance of special reviews and investigations and reports f

thereon as requested by the Chairman of.the Nuclear Review Board.

1.

Render determinations in writing-with regard to whether or not each -

=-

item considered under-6.5.1.6(a) through (e) above constitutes an unreviewed saf ety questions.

!o MILLSTONE - UNIT 1 G6 l

t s.

I I,

ADMINISTRATIVE CONTROLS REVIEW 6.5.3.6 The NRB shall review:

The safety evaluation for 1) changes to procedures, equipment or a.

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 unre(pre (safety questions as defined in Section 50.59,10CFR.

Proposed tests or experiments which involve an unreviewed safety c.

question as defined in Section 50.59,10 CFR.

d.

Proposed changes in Sections 1.0 5.0 of these Technical

~

Specifications or licenses, e.

Violations of applicable statutes, codes, regulations, orders, e

Technical Specifications,. license requirements, or of internal procedures or instructions having nuclear safety significance.

f.

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

g.

All REPORTABLE EVENTS.

s h.

Indications of a significant unanticipated deficiency, affecting nuclear saf ety, in some aspect of design or operation of safety.

related structure, systems or components.

1.

Report and meetings minutes of the PORC.

e AUDITS 6.5.3.7 Audits of Unit activities shall be performed under the cognizance of the NRB. These audits shall encompass:

The conformance of Unit operation to provisions contained within the;" ~~ ~~-

a.

Technical Specifications and applicable license. conditions at~ least once per 12 months.

e e

Mii LSTONE - UNIT 1 6-11

• er 4

a:

Y.

\\

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.4.8 The SNRB reports to and advises the Senior Vice President ' Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.4.6 and 6.5.4.7. Meeting minutes may be used for this purpose.

' RECORDS 6.5.4.9 Records of SNRB activities shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations

=

within 14 days iollowing each meeting.

Minutes of each SNRB meeting shall be prepared; approved, and a.

forwarded to the Senior Vice President Nuclear Engineering. and Operations within 14 days following each meeting.

b.'

Reports of reviews encompassed by Section 6.5.4.6 above shall be prepared, approved, and forwarded to the Senior Vice President

-Nuclear Engineering and : Operations within 14 -' days following completion of the review.

c.

Audit reports encompassed by Section 6.5.4.7 above, shall be forwarded to the Senior Vice President Nuclear Engineering and Operations and to the management positions responsible for the areas audited within 30 days af ter completion of the audit.

6.6 REPORTABLE EVENT ACTION 8

6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

The Commission shall be notified and a report submitted pursuant to a.

the requirement of Section 50.73 to 10 CFR Part 50, and b,

Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NRB and the Vice President Nuclear Operations.

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

The unit shall be placed in at least HOT SHUTDOWN within two a.

hours.

MILLSTONE - UNIT 1 6-15 4D 4

e

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

The intent of original procedure is not altered.

a.

1 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 PORC/SORC, as applicable, and approved' by the Unit Superintendent / Station -

Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREMENTS

_ ROUTINE REPORTS 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 Regional Administrator, Region I, U. S. Nuclear Regulatory Commission unless otherwise -

noted.

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

6.9.1.2 The startup 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 ~ specifications. - Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

'9 e

s D

9 MILLSTONE - UNIT 1 6-17 s

=

ADMINISTRATIVE CONTROLS 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 Resource Management, U. S. Nuclear Regulatory Commission,' Washington, D.-C. 20555,-

with a copy to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission,no later than the 15th of each month following the calendar month covered by the report.

I SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region 1, U. S. Nuclear Regulatory Commission, within the time period specified for each report.

These reports shall be submitted. covering the activities- -~='

identified below pursuant to the requirements of the applicable reference specification:

, a.

In-service Inspection Results, Specification 4.6.F.

~.

b.

' Primary Containment Leak Rate Test Results, Specification 4.7.A.3.

.c.-

(Deleted).

d.

Materials Radiation Surveillance Specimen Examination and Results,-

Specification 4.6.B.5.

e. ' lire detection instrumentation, Specification (3.12.E.2).

~

-x f.

Fire suppression *i ste'ms, Specifications (3.12.A.2, 3.12.B.2, 3.12.C.2 g~ *'..

i

,,, and 3.12.C.4).

O eir l.

MILLSTON.E - UNIT 1 6-19 e

h v.

-~

e e-ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

Records and logs of facility operation covering time interval at each -

a.

power level.

b.

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

c.

All REPORTABLE EVENTS.

d.

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

Records of reactor tests and experiments, e.

f.

- Records of changes made to operating procedures.

g.'

Records of radioactive shipments.

h. -

Records of sealed source leak tests and results.

.l.

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

- Jhe foIlowing records shall be retained for the digon.of.the 6.10.2 facility operating license:

. s Records and drawing changes reflecting facility design modifications a.

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.

Records of f acility radiation and contamination surveys.

c.

d.'

Records of radiation exposure for all individuals entering radiation ~

control areas.

g.

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

. environs.

f.

Records 'of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

MILLSTONE - UNIT 1 6-20 Y Q 4

.4 9

q 4

l ADMINISTRATIVE CONTROLS g.

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

h.

Records of inservice 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 Part 50.59.

k. - Records of meetings of the PORC, the NRC, the SORC and the SNRB.

1.

Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

6.11 RADIATION PROTECTION PROGRAM.

Procedures for personnel radiation protection shall be prepared consistent with

- the requirements of 10 CFR ~Part 20 and shall be approved, maintained.and

- adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of. the " control device" or " alarm signal" required by paragraph 20.203(cX2) of 10CFR20, each high radiation area in which the intensity of.

radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be

.. barricaded and conspicuously posted as a high. radiation area and entrance thereto shall be controlled by 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 th,e 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 integrated dose is received. Entry into such areas with this monitoring device may be made af ter the ' ose rate level in the area has been d

established and personnel have been made knowledgeable of them.-

• Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved--

radiation protection procedures for entry into high radiation areas.

MILLSTONE - UNIT 1 6-21

• ee 9

^

,,r_m_

- - - - - +-,-.,

_y,.,

1-<-,

r-*

,y--,m

ADMINISTRATIVE CONTROLS An individual qualified in radiation protection procedures who is c.

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 perform periodic radiation - --

surveillance at the frequency specified in the Rdiation Work Permit.

The surveillance frequency shall be established by the Health Physics Supervisor.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 100 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 Shif t Supervisor on duty and/or the Health Physics Supervisor.

Y%

^

9

+

g.n

-~

MILLSTONE - UNIT 1 G-22

.. ~,

,e *g,

I

4 6.13 ENVIRONMENTAL QUALIFICATION A.

By no later than June 30,1982 all safety-related electrical eguipment in the facility shall be qualified in accordance with the provisions of:

. Division of Operating Reactors

" Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors (DOR Guidelines); or, NUREG-0588 -" Interim ~ % c m.

Staff. Position on Environmental Qualification of Safety-Related Electrical Equipment", December 1979. Copies of these documents are attached to Order for Modification of License DPR-21 dated October 4,1980.

B.

By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe - -

the environmental qualification method used for all safety-relatedr=m---

electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Thereafter,-

such records should be updated and maintained current as equipment

~

is replaced, further tested, or otherwise further qualified.

,6.14 SYSTEMS INTEGRITY.

The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during ~ r a serious transient or accident to as low as practical levels. This program shall include the following:

1.-.

Provisions establishing preventive mai[1tenance and periodic visual 3,, -

inspection requirements, and 2.

Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

6.15 IODINE MONITORIN_G The licentee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shallinclude the following:

1.

Training of personnel, 2.

Procedures f or monitoring, and 3.

Provisions for maintenance of sampling and analysis equipment.

pg ' '

v.

MILLSTONE - UNIT 1 6-23 4.

(4 Docket No.~ 50-336 1

Proposed Revisions to Technical Specifications Millstone Nuclear Power Station, Unit No. 2 k

,.'y 4

July,1985

4-INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS Defined Terms.....................................

1-1 Thermal Power.....................................

1-1 Rated Thermal Power...............................

1-1 Operational Mode..................................

1-1 Action............................................

1-1 Operable - Operability............................

1-1 Reportable Event..................................

1-1 l

Containment Integrity....'.........................

1-2 Channel Calibration...............................

1-2 Channel Check 4........................-............

1-2 Channel Functional Test..........................

1-2 Core Alteration...................................

1-3 Shutdown Margin'...................................

1-3 Id en ti fied Le akage................................

1-3 Unidentified Leakage..............................

1-3 Pressure Boundary Leakage.........................

1-3 Controlled Leakage................................

1-3 Azimuthal Power Tilt...............................

1-4 Dose. Equivalent I-131.............................

1-4

- s' E-Average Disintegration Energy..................

1-4 Staggered Test Basis.............................

1-4 Fr eq ue ncy No ta tion................................

1-4 Axial Shape Index..................................

1-5 Un' rodded Planar Radial Peaking Factor - Fxy '.......

1-5 Enclosure Building Integrity.......................

1-5 Reactor Trip System Response Time.................

1-5 d

Engineered Safety Feature Response Time...........

1-5 Phy sic s T es ts......................................

1-6 Unrodded Integrated Radial Peaking Factor - F 1-6 r....

I

- MILLSTONE - UNIT 2 bk e

c.

l-INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 5.9 REPORTING REQUIREMENTS 5.9.1 ROUTINE REPORTS.................................

6-17 5.9.2 SPECIAL REPORTS.................................

6-19 5.10 RECORD RETENTION................................

6-20 5.11 RADIATION PROTECTION PROGRAM.....................

6-21 5.12 HIGH RADIATION AREA..............................

6-21 5.13 ENVIRONMENTAL QUALIFICATION......................

6-22 5.14' SYSTEMS INTEGRITY................................

6-22 5.15 IODINE MONITORING................................

6-23 1

e O

4 e

W t.

e a

D S

XVII MILLSTONE - UNIT 2 O

h-g

1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL-POWER 1.2 THERMAL POWER shall be the total reactor core heat transf er rate to the reactor coolant.

RATED THERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.

4 OPERATIONAL MODE -

~ 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination -

of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1. -

ACTION 1.5 ACTION shall be those additional requirements specified as corollary

, statements to each principal specification and shall be part of the specifications.

. OPER ABLE - OPERABILITY 1.6 A system, subsystem, train, component, or device shall be OPER ABLE or have OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling, or seal water, lubrication, or other auxiliary equipment that are required for the system, subsystem, train, component, or -

device to perform its f unction (s) are also capable of performing their related support function (s).

REPORTABLE EVENT 1.7 'A' REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

p

.+

s MILLSTONE - UNIT 2 1-1 f.

a

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zene shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number of OPERABLE requirements of Table 3.3-10.

Within I hour establish a fire watch patrol to inspect the zone (s)

-~

a.

with the inoperable instrument (s) at least once per hour, and

'b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.6.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REOUIREMENTS 4.3.3.7.1 Each of the above required fire detection instruments shall be demonstrated OPERABLE at ler.t once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.

4.3.3.7.2 The circuits between the above required detection instruments and the control room shall be demonstrated OPERABLE at least once per 31 days per approved procedures.

S MILLSTONE - UNIT 2 3/4 3-43 4

4 6

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.5 Reports Following each inservice inspection of steam generator tubes, the a.

number of tubes plugged and sleeved in each steam generator shall be reported to the Commission within 15 days.

b.

The complete results of the steain generator tube inservice inspection shall be included in the Annual Operating Report for the ~~

period in which this inspection was completed. This report shall include:

1.

Number and extent of tubes inspected.

2.

Location and percent of wall-thickness penetration fer each indication of an imperfection.

3.

Identification of tubes plugged or sleeved.

Results of steam generator tube inspections which fall into -

c.

u-

~1 Category C-3 shall be reported pursuant to 10CFR50.72. In lieu ^ ~

of any report required pursuant to Specification 6.6.'1, a Special Report pursuant to Specification 6.9.2 shall be submitted. prior to resumption of plant operation and shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.

. ' * ', eh 4

81 s

e MILLSTONE - UNIT 2 3/4 4-7b 4

• A

k REACTOR COOLANT SYSTEM hh SPECIFIC ACTIVITY s

LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limifed to:

a. 11.0 Ci/ gram DOSE EQUIVALENT l-131, and

b., i 100/E Ci/ gram.

j APPLICABILITY: MODES 1,2, 3, 4 and 5.

e.,,,.

ACTION:

4 MODES 1,2 and 3*:

With the specific activity of the primary coolant >1.0pCi/ gram a.

DOSE EQUIVALENT I-131 but within the allowable limit (below and -

to the lef t of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that operation tmder these r n "I =

circumstances shall not exceed 10 percent of ths, unit's total yearly -- '

operating time. The provisions of Specification 3.0.4 are not - - '

applicable.

A b.

With the specific activity of the primary coolant > 1.0pCi/ gram DOSE EQUlvALENT l-131 ior more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during onen --

continuour, time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with Tavg<5150F within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ~ ~-

With the specific activity of the primary coolant >100/E y Ci/ gram, c.

be in HOT STANDBY _with Tavg <515 F within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i MODES 1, 2, 3, 4 and 5:

/

d.

With the specific activity of the primary coolant > 1.0 uCi/ gram DOSE EQUIVALENT I-131 or > 100/E y Ci/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-2 until the specific activity of the primary coolant is restored to within its -

limits. A Special Report shall be prepared and submitted 4othe -=

Commission pursuant to Specification 6.9.2. This report shall -

contain the results of the specific activity analyses together with the following information:

+With Tavg.)_5150F.

e MILLSTONE '- UNIT b 3/4 4-13

g. -

___ __ ____ _ _ _ _ _ _ ____ -. _ _ _ _ ____ _ _. _ _ _ _. _ _._ _ ____. d

R i

CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

' b.

Removing one wire from a dome, a vertical and a hoop tendon checked for lif t off force pursuant to Specification 4.6.1' 6.1.a and -

determining that over the entire length of the removed wire that:

1.

The tendon wires are free of corrosion.

2.

There are no changes in physical appearance of the sheathing

~

filler grease.

3.

A minimum tensile strength of 11,760 pounds for at least three wire samples (one from each end and one at mid-length) cut from each removed wire. Failure of any one of the wire samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.

4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces The structtral -

integrity of the end anchorages and adjacent concrete surfaces shall:be 7 r

~

demonstrated by determining through inspection that no apparent changes have u

occurred in the visual appearance of the end anchorage concrete exterior a

_~

surfaces or the concrete crack patterns adjacent to the end. anchorages.-~-- -

- Inspections of the concrete shall be performed during the Type A containment m: m -

leakage rate tests (reference Specification 4.6.1.2) while the containment is at lts maximum test pressure.

+

.4.6.1.6.3 Liner Plate The structural integrity of the containment liner plate-shall be determined during the shutdown for each Type A containment leakage

' rate test (reference Specification 4.6.1.2) by a visual inspection of the plate and ~~

verifying no apparent changes in appearance or other abnormal degradation.

4 4.6.1.6.4 Reports in lieu of any other report required by Specification 6.6.1, an.

Initial report of any abnormal degradation of the containment. structure detected.

during the above required tests and inspections shall be made within '10 days ~

af ter completion of the surveillance requirements of this specification and the -- '

detailed report shall be submitted pursuant to Specification 6.9.2 within 90 days after completion. This report shall include a description of the condition of the.,

]

concrete (especially at tendon anchorages), the inspection procedure, the tolerances on cracking, and the corrective actions taken.

r

MILLSTONE - UNIT 2 3/4 6-11

,.y,-

' 'T u

- le.

9

. PLANT SYSTEMS 3/4.7.9 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9.1 The fire suppression water system shall be OPERABLE with:

Three high pressure pumps, each with a capacity of at least 1800 a.

gpm, with their discharge aligned to the fire suppression header, -

L l

'b.

Two water supplies, each with a minimum contained volume of 200,000 gallons, and An OPERABLE flow path capable of taking suction from the fire c.-

water tanks and transferring the water through distribution piping -

i, with OPERABLE sectionalizing control or isolation valvesto the yard u

(

hydrant curb valves andthe first valve ahead of the water flow-alarm z===

device on each sprinkler, hosestandpipe or spray-system riser

~ ~

~~

required to be OPERABLE per Specifications 3.7.9.2 and 3.7.9.3.-

APPLICABILITY: At all times.

[

ACTION:

With one pump and/or one water supply inoperable, restore the' a.

inoperable equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.6.1, prepare and

-l 4

submit a Special Report to the Commission pursuant to Specification'~=

6.9.2 within the next 30 days outlining the plans and procedures.to be: - -

used to provide for the loss of redmdancy in this system. The.

l

. provisions of Specifications 3.0.3 and 3.0.4 are n:t applicable.

b.

- With two pumps inoperable, establish a continuous fire watch of the turbine building with backup fire suppression equipment within I hour; restore the inoperable equipment to OPERABLE status within.

14 days or, in lieu of any other report required by Specification 6.6.'1,'.

- ue l

prepare and submit a Special Report to the Commission pursuant to,

Specification 6.9.2 within the next 30 days outlining 1he' action taken, the cause of the inoperability and the plans and schedule for restoring the equipment to OPERABLE status. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

MILLSTONE - UNIT 2 3/4 7-33 w.

yr w--i

e PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.9.2 The following spray and/or sprinkler systems shall be OPERABLE:

a.

Diesel Generator Rooms b.

Diesel Generator Day Tank Rooms c.

Cable Vault (Aux. Building) d.

Cable Vault (Turbine Building) e.

Hydrogen Seal Oil Unit f.-

Turbine Building Northeast Corner g.:

Turbine Building 31'6"/14'6"- North -

h.

Turbine Building 31'6"/l4'6"- South i.

Lube Oil Room.

/.PPLICABILITY: Whenever equipment in the spray / sprinkler protected areas is required to be OPERABLE.

ACTION:

With one or more of the above required and/or systems inoperable,'

a.

"z c

establish a continuous fire watch with backup fire suppression 7 - -

equipment for the unprotected area (s) within :1 hour; restore the 1

(~

- system to OPERABLE status within 14 days or,in lieu of any other '

report required by Specification 6.6.1, prepare and submit a Special l

Report to the Commission pursuant to Specification 6.9.2 withinthe-next 30 days outlining the action taken, the cause of the inoperability -

and the plans and schedule for restoringthe system to OPERABLE '

status.

4 b.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.9.2 Each of the above required spray and/or sprinkler systems shall be l-tiemonstrated OPERABLE:

i MILLSTONE - UNIT 2 3/4 7-37 O_

u REACTOR COOLANT SYSTEM BASES evidence of mechanical damage or progressive degradation due to design,

~

manufacturing errors, or inservice conditions that lead to corrosion. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and catse of any tube degradation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant ~~ ~~

chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.

The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 0.5 GPM, per -

steam generator).

Cracks having a primary-to-secondary leakage less than this- -

~

limit during operation will have an adequate margin of safety to withstand 1he~

loads imposed during normal operation and by postulated accidents.1 Operating ~ =

plants have demonstrated that primary-to-secondary leakage of '0.5 gallon Per_ -

1 m,inute can readily be detected 'by radiation monitors of steam generator-blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.

Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will:

r

- ~

l be found during scheduled inservice steam generator tube examinations.

Plugging or slee the plugging lim,ving will be required for all tubes with imperfections exceeding-it of 40% of the tube nominal wall thickness. Sleeving repair

- will be limited to those steam generator tubes with a defect between the tube -

sheet and -the first eggcrate support.

Tubes containing sleeves -with:.-

1 imperfections exceeding the plugging limit will be plugged. Steam generatortube-

~

inspections of operating plants have demonstrated the capability of reliably detect degradation that has penetrated 20% of the original tube wall' thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be immediately reported -to the Commission pursuant to 10 CFR 50.72. Such cases will be considered by the g

. Commission on a case-by-case basis and may result in a requirement-for analysis, -

-laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications,if necessary.

B 3/4 4-2a MILLSTONE - UNIT 2 M

O Me

~

--_,--s

e ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman.

QUORUM 6.5.1.5 A quorum of the PORC shall consist of the Chairman or Vice Chairman or Station Superintendent and four members including alternates.

- RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for:

Review of 1) all procedures, except common site procedures, required a.

by Specification 6.8 and changes.thereto, 2) any other proposed procedures or changes thereto as determined by the Unit Superintendent to affect nuclear safety.

b.

Review of all proposed tests and experiments that affect nuclear.

safety.

?

^

Review of all proposed changes to Sections 1.0 - 5.0 of those c.

Technical Specifications.

d.

. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear saf ety.

F i

e.

Investigation of all violations -of the Technical Specifications and

[

preparation and forwarding of a report covering evaluation and-i-

recommendations to prevent recurrent to the Vice President Nuclear l

Operations and to the Chairman of the Nuclear Review Board.

f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential safety hazards.

h.

Performance of special reviews and investigations and reports

. thereon as requested by the Chairman of the' Nuclear Review Board.

(-

i.

Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitut,es an unreviewed saf ety. questions.

s.

l l

66 MILLSTONE - UNIT 2

,,...., ~

a L-_._

u ADMINISTRATIVE CONTROLS REVIEW 6.5.3.6 The NRB shall review:

The safety evaluation for 1) changes to procedures, equipment or a.

systems and 2) tests or experiments completed under the provision of Section 50.59,10CFR, to verify that such actions did not constitute an mreviewed safety question.

b.

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

Proposed tests or experiments which involve an unreviewed safety -

c.

question as defined in Section 50.59,10 CFR.

. d.

Proposed changes in Sections 1.0 5.0 of these Technical Specifications or licenses, e.

Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear saf ety significance.

f.

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

g.

All REPORTABLE EVENTS.

h.

Indications of a significant unanticipated deficiency, affecting nuclear safety, in some aspect of design ~ or operation of -safety related structures, systems or components.

. i.

Report and meetings minutes of the PORC.

AUDITS k

6.5.3.7 Audits of facility activities shall be performed under the cognizance of the NRB. These audits shall encompass:

The conformance of facility operation to all provisions contained

~

a.

within the Technical Specifications and applicable license conditions at least once per year.

i w: 6-11 MILLSTONE - UNIT 2

\\s__

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.4.8 The SNRB reports to and advises the Senior Vice President Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.4.6 and 6.5.4.7. Meeting minutes may be used for this purpose.

RECORDS 6.5.4.9 Records of SNRB activities shall be prepared, approved, and distributed as indicated below:

Minutes of each SNRB meeting shall be prepared; approved, and a.

forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.4.6 above shall be prepared, approved, and forwarded to the Senior Vice President -

Nuclear Engineering and Operations within 14 days following completion of the review.

c.

Audit reports encompassed by Section 6.5.4.7 above, shall-be l

forwarded to the Senior Vice President Nuclear Engineering and Operations and to the management positions responsible.for the areas -

audited within 30 days af ter completion of the audit.

~ 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

The Commission shall be notified and a report submitted pursuant to a.

the requirement of Section 50.73 to 10 CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the PORC and the j

results of this review shall be submitted to the NRB and the Vice President Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION l

l 6.7.1 The following actions shall be taken in the event a Safety Limit is

~

violated:

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

a.

l i

j 6-15 j

' MILLSTONE - UNIT 2 i

e L_

^

ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

The intent of original procedure is not altered.

a.

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 PORC/SORC, as- -.

applicable, and approved by the Unit -- Superintendent / Station ~ ~

Superintendent within 14 days of implementation.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted -to Regional Administrator, Region I, U. S. Nuclear Regulatory Commission unless otherwise -

noted.

STARTUP REPORT

. 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the r

license involving a planned increase in power level, (3) installation of fuel that

. has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal or hydraulic performance of the plant.

6.9.1.2 The startup 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- :=

l' of these values with design predictions and specifications.

Any corrective l

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 included in this report.

l I

e 4-

~~

/

6-17 MILLSTONE - UNIT 2

. w wy,-

ein

--ywwwwrw,,,

w

-w_-^,w

,,www yww-m

^

. - e ADMINISTRATIVE CONTROLS 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,' U.~ S..

~

Nuclear Regulatory Commission, Washington, D. C. 20555, with a copy to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, no later than the 15th of each month following the calendar month covered by the report.

SPECIAL REPORTS,,

6.9.2 Special reports shall be submitted to the Regional Administrator, Region I, U. S. Nuclear Regulatory Commission, within the time period specified for each report.

These reports shall be submitted covering the activities -

identified below pursuant to the requirements of the applicable reference specification:

Inoperable Seismic Monitoring Instrumentation, a.

Specification 3.3.3.3.

b.

Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

Safety Class 1 inservice Inspection Program Review, Specification c.

4.4.10.1.

d.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

Fire Detection Instrumentation, Specifications 3.3.3.7.

e.'

f.

Fire Suppression Systems, Specifications 3.7.9.1 and 3.7.9.2.

g.

RCS Overpressure Mitigation, Specification 3.4.9.3 h.'

Specific activity levels, Specification 3.4.8.

i.

Degradation of containment structure, Specification 4.6.1.6.4.

j.

Steam Generator Tube Inspection, Specification 4.1.5.1.5.

• W I'

i L'

6-19 MILLSTONE - UNIT 2 e.

t_

{

.., o e

ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

Records and logs of facility operation covering time interval at each a.

power level.

b.

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

All REPORTABLE EVENTS.

d.

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

Records of reactor tests and experiments.

e.

f.

Records of changes made to operating procedures.

g.

Records of radioactive shipments.

~

h.

Records of sealed source leak tests and results.

i.

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:

t Records and' drawing changes reflecting facility design modifications a.

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.

Records of f acility radiation and contamination surveys.

c.

d.

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

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

environs.

f.

Records of transient or operational cycles for ' those facility components designed for a limited number of transients or cycles.

6-20 MILLSTONE - UNIT 2 mO' *

._.-n-,

- o

,o

~

v ADMINISTRATIVE CONTROLS g.

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

h.

Records of inservice 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 Part 50.59.

k.

Records of meetings of the PORC, the NRC, the SORC and the SNRB.

1.

Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.

6.11 RADIATION PROTECTION PROGRAM

+

Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10CFR20, each high radiation area in which the -intensity of--~

'~'

radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a-high - radiation area and entrance- ~

thereto shall be controlled by 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 radiation monitoring device which continuously indicates the a.

radiation dose rate in the area.

b.

A radiation monitoring device which continuously integrates the er 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.

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

4 6-21

,m MILLSTONE - UNIT 2

,,u

e

,o.* o ADMINISTRATIVE CONTROLS An individual qualified in radiation protection procedures who is c.

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 perform periodic radiation -

surveillance at the frequency specified in the Rdiation Work Permit.

The surveillance frequency shall be established by the Health Physics Supervisor.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 100 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 Shif t Supervisor on duty and/or the Health Physics Supervisor.

6.13 ENVIRONMENTAL QUALIFICATION 6.13.1 By no later than June 30,1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: -Division of ' ~

Operating Reactors " Guidelines for Evaluating Environmental Qualification of-Class IE Electrical Equipment in Operating Reactors" (DOR-Guidelines); or, NUREG-0588 " Interim Staff Position on Environmental-Qualification of Safety r ~

Related Electrical Equipment", December 1979. Copies of these documents are attached to Order for Modification of License DPR-65 dated October 24,1980.

6.13.2 By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detall to document the degree-of-compliance-with1he - ~

DOR Guidelines or NUREG-0588. Thereaf ter,'such records should be updated and maintained current as equipment is replaced, further tested, or otherwise

.further qualified.

6.14 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems

~

outside containment that would or could contain highly radioactive fluids during - - - - '

a serious transient or accident to as low as practicallevels. This program shall t

include the following:

I 1.

Provisions establishing preventive maintenance and periodic visual l

Inspection requirements, and 1

2.

Integrated leak test requirements for each system at a frequency not

. to exceed ref ueling cycle intervals.

1. p-l l

6-22 MILLSTONE - UNIT 2 l

r

(

7-.

c'e O ADMINISTRATIVE CONTROLS 6.15 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under'~

~

accident conditions. This program shallinclude the following:

1.

Training of personnel, 2.

Procedures for monitoring, and 3.

_ Provisions f or maintenance of sampling and analysis equipment.

e

• y e

o 6

@s

,34 s

o 6-23 l

MILLSTONE - UNIT 2

,3

+

..m w

i J b,.

A