Text

Amends 33 & 13 to Licenses NPF-4 & NPF-7,respectively, Revising Inservice Surveillance Requirements for safety- Related Snubbers Effective 811120
	ML20033C426
Person / Time
Site:	North Anna
Issue date:	11/05/1981
From:	Clark R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20033C427	List: ML20033C426; ML20033C430; ML20033C431;
References
	NUDOCS 8112030186
	Download: ML20033C426 (48)
	v • d • e

,

4,,#c UNITED STATES

_g y

g NUCLEAR REGULATORY COMMISSIC N D

< p WASHINGTON, D. C. 20555 4

9.....,o VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 NORTH ANNA POWER' STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33-License No. NPF-4 1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated July 1,1981 as supplemented by letter dated September 10. 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations ~ set forth in 10 CFR Chapter I; B.

The facility v fil operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without er.dangering the health and safety of the public, and (ii) that such activities will be conducted in comp!iance with the Connission's regulations; D.

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

c-8112030186 811105 PDR ADOCK 05000338 P

PDR

. t 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices -

A and B, as revised through Amendment No. 33, are hereby incorporated in the' license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective on November 20, 1981.

FOR THE NUCLEAR REGULATORY COMMISSION N

ark, Chief o

Operating Reactors Branch #3 -

X Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 5, 1981 c~

.4

ATTACHMENT TO LICENSE AMENDMENT

'AFENDMENT NO. 33 TO FACILITY OPERATING LICENSE N0. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and co.ntain vertical lines ind.icating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages Pages XIX 3/4 7-48 3/4 3-22 3/4 7-49 3/4 3-26a 3/4 7-50 3/4 3-33 3/4 7-51 3/4 7-28 9

3/4 7-52 3/4 7-29 3/4 7-53 3/4 7-29a 3/4 7-53a 3/4 7-29b-add 3/4 7-53b 3/4 7-29c-add 3/4 7-54 3/4 7-30 3/4 7-55 3/4 7-31 3/4 7-56 3/4 7-57 3/4 7-32 3/4 7-33 3/4 7-58 3/4 7-34 3/4 7-59 3/4 7-35 3/4 7-60 3/4 7-36 3/4 7-61 3/4 7-37 3/4 7-62 3/4 7-38 3/4 7-63 3/4 7-39 3/4 7-64 3/4 7-40 3/4 7-65 3/4 7 41 3/4 7-65a 3/4 7-42 3/4 7-65b 3/4 7-43 3/4 7-65c 3/4 7-44 3/4 7-66 3/4 7-45 83/47-6 3/4 7-46 83/47-7 3/4 7-47 6-14 6-21 6-22

<r

INDEX b.,

ADMINISTRATIVE CONTROLS SECTION PAGE Consultants.....................................................

6-8 Meeting Frequency................

6-8 Review.........................

6-8 Authority........................

6-9 Records.......................................

6-9 6.5.3 QUALITY ASSURANCE DEPARTMENT Function...........................................

6-10 Authority....................................................

6-10 Records............................

6-11 r

6. 6 REPORTABLE OCCURRENCE ACTION..................

6-12 6.7 SAFETY LIMIT VIOLATION.

6-12 6-13 6.8 PROCEDURES AND PROGRAMS.

6.9 REPORTING REQUIREMENTS 6.9.1 RCUTINE REFORT5 AND REFERTABLE OCCURRENCES.

6-14 6.9.2 SPECIAL REPORTS.

6-18 6-20 6.10 RECORD RETENTION.

S.11 RADIATION PROTECTION PROGRAM.

6-21 6.12 HIGH RADIATION AREA...............

6-22 c-6.13 ENVIRONMENTAL QUALIFICATION....

6-23 NORTH ANNA-UNIT 1

.XIX Amend.nent ;o. E, 30, 37, 33

TABLE 3.3-3 (Continued) l TABLE NOTATION

Trip function may be blocked in this MODE below P-ll.

1. Trip function may be blocked in this MODE below P-12.

NThe channe'.ts) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped l

mode.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 13 -

With the number of OPERABLE Channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

I ACTION 14 -

With the number of OPERABLE Channels one less than the' Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST, provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 15 -

With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in HOT SHUTDOWN with-:n the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

ACTION 16 -

With the number of OPERABLE Channals one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the blocked condition and the Minimum Channels OPERABLE requirement is demon-strated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; one additional channel may be blocked for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

e NORTH ANNA-UNIT 1 3/4 3-21 d

8 TABLE 3.3-3 (Continued)

ACTION 17 -

With the number of OPERABLE Channels one less than the Total Number of Channels operation may proceed provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and the Minimum Channels OPERABLE requirement is met, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.1.

l ACTION 18 -

With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN' within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 ACTION 19 -

With the number of OPERABLE Charnels one less than the Total Number of Channels, STARTl'? and/or POWER OPERATION i

may proceed provided the folloning conditions are satisfied:

j a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

i i

I b.

The Minimum Channels OPERABLE requirements is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months "for surveillance testing per Sp.cification 4.3.2~.1.1.

ACTION 20 -

With the number of OPERABLE Channels one less than the Total Number of Channets, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to I hour for surveillance testing per Speci fication 4.3.2.1.1 provided the other Ch?nm i is OPERABLE.

ACTION 21 -

With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable Channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

v~

NORTH ANNA-UNIT 1 3/4 3-22 Amendment No. )%, 33

1 I

5 C

l TABLE 3.3-4 (Continued) 3E 5

ENGINEERED SAFETY FFATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS g'

C e

3 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

--4

~

1 6.

AUXILIARY FEEDWATER PUMP START a.

Manual N. A.

N. A.

b.

Automatic Actuation Logic N. A.

N. A.

9 c.

Steam Generator Water 2 IS%iof narrow range 217% of narrow range.

Level Low-Low instrument span each instrument span each steam generator steam generator d.

S.I.

See 1 above (All S.I.. Setpoints)

't e.

Station Blackout 2 57.5% Transfer Bus Voltage 2 52.5% Transfer Bus Voltage w

f.

Trip of Main Feed Pump N. A.

N. A.

Y M

7.

LOSS OF POWER w

a.

4.16 kv Emergency Bus Undervoltage 2999 60 volts with a 2912 i 60 volts with a (Loss of Voltage) 2.2 1 0.03 second time delay 3 1 0.03 second time delay b.

4.16 kv Emergency Bus Undervoltage 3744 i 1.4 volts with a 3619 i 1.4 volts with a (Degraded Voltage) 60 i 3 second time delay 75 i 3 second time delay e

=

1 N

O.)

l-i

=

S

-4 x

TABLE 4.3-2 (Continued) 3 a

=

l

' ENGINE.ERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SUitVE1LLANCE REQUIREMENTS c-MODES IN WIIICH

.s

=

CHANNEL y

C!IANKr.L CIIANNEL FUNCTIONAL SURVEILLANCE i

FUNCTIONAL UNIT CIIECK CALIBRATION TEST REQUIRED 5.

TURBINE TRIP AND FEEDWATER l

ISOLATION a.

Steam Generator Water S

R H

1,2,3 Levei--High-liigh 6.

AUXILIARY FEEDWATER PUMPS a.

Manual N. A.

N. A.

11(1) 1, 2, 3 w

b.

Automatic Actuation N. A.

N. A.

M(2) 1, 2, 3 g)

Logic c.

Steam Generator Water S

R H

1,2,3,4 l

[

w Level--Low-Low d.

S.I.

See 1 above (all S.I. Surveillance Requirements) e.

Station Blackout N. A.

R N. A.

1, 2, 3, 4 l

f.

Main Feedwater Pump N. A.

N. A.

R 1, 2 Trip y,

$g 7.

LOSS OF POWER g

4.16 KV Emergency Bus 5

a.

Loss of Voltage N. A.

-R M(2),

1, 2, 3 O

b.

Degraded Voltage N. A.

R M(2) 1, 2, 3

?

1",

l

4 i

TABLE 4.3-2 (Continued) f TABLE NOTATION (1) Manual actuation switches shall be tested at least once per 18 months-during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once every other 31 days.

(2) Each train or logic channel shall be tested at least every other -

31 days.

I (3) The CHANNEL FUNCTIONAL TEST'shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

l NORTH ANNA.- UNIT 1 3/4 3-34'

PLANT 4YSTEMS RHR - SHUTDOWN i

LIMITING CONDITION FOR OPERATION 3.7.9.2 As a minimum, one residual heat removal subsystem shall be OPERABLE.

APPLICABILITY: MODES 4 and 5.

ACTION:

With no Residual Heat Removal subsystem OPERABLE, immediately restore at least one RHR subsystem to OPERABLE status or maintain the Reactor Coolant System T less than 350.F by use of alternate heat removal l

methods. The prNisions of Specifications 3.0.3, 3.0.4 and 4.0.4 are j

not applicable.

SURVEILLANCE REQUIREMENTS 4.7.9.2 Each Residual Heat Removal" subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirement of Specification 4.7.9.1, and a.

At least once per 31 days by';

1.

Cycling each testable, remote or automatically operated valve through at least one ccmplete cycle, and 2.

Verifying the correct position of each. manual valve not locked sealed or otherwise secured in position, and 3.

Verifying the correct position of each remote or auto-matically operated valve.

NORTH ANNA - UNIT 1 3/4 7-27 tmendment No. 3

PLANT SYSTEMS 3/4.7.10 5 UBBERS LIMITING CONDITION FOR OPERATION 3.7.10 All snubbers listed.in Tables 3.7-4s and 3.7-4b shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

With orie or more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.10.c on the supported component or declare the supported

' system inoperabia and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program,and the requirements of Specification 4.0.5.

a.

Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.

If less than two (2) snubbers are found inoperable during the first inservice visual inipection, the second inservice visual inspection shall be performed 12 months 25% from the date of the first inspection. Othenise, subsequent visual inspections shall be performed in accordance with the following schedule:

No. Inoperable Snubbers Subsequent Visual per Inspection Period Inspection Period *y 0

18 months 2 25%

1 12 months i 25%

2 6 months i 25%

3,4 124 days i 25%

5,6,7 62 days i 25%

8 or more 31 days i 25%

~

The snubbers may be categorized into two groups:

Those accessible and those inaccessible during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

n The inspection interval shall not be lenthened more than one step at a timt.

g The provisions of Specification 4.0.2 are not applicable.

NORTH ANNA - UNIT 1 3/4 7-28 Amendment No. 33

~

PLANT' SYSTEMS SURVEIL'tANCE REQUIREMENTS (Continued) b.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visual indica-tions of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without

" disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.

Snutbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and reme8ied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition ano determined OPERABLE per Specifi-cations 4.7.10.d and 4.7.10.e.

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

All snubbers connected to an inoperable common hydraulic fluid reservior shall be cours. as inoperable snubbers.

c.

Functional Tests At least once per 18 months during shutdown, a representative sa ple of that number of snubbers which follows the expression 35 [1 +

),

wheN c='2 % the allowable number of snubbers not meeting the acceptance criteria selected by the operator, shall be functionally tested either in place or in a bench test.

For each number of snubbers above c which does not meet the functional test accept.ance criteria of Specification 4.7.10.d or 4.7.10.e, an additional cample selectedaccordingtotheexpressior35(1+[](c 1)

(a c) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample.

Functional testing shall continue according to the expression b[35(1+j)2]wherebisthenumberofsnubbersfound inoperable in the previous re-sample, until no additional c~

inoperable snubbers are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested.

NORTH ANNA - UNIT 1 3/4 7-29 Amendment No. 33 ee

PLANT SYSTEMS SURVEILt.ANCE REQUIREMENTS (Continued)

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

1.

The first snubber away from etch reactor vessel nozzle 2.

Snubbers within 5 feet of heavy equipment (valve, pump, turbine, motor,etc.).

3.

Snubbers within 10 feet of the discharge from a safety relief valve.

Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in "High Radietion Zones During Shutdown" shall also be included in the representative sample.* Tables 3.7-4a and 3.7-4b may be used jointly or separately as the basis for the sampling plan.

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare :.aubber has been insta,lled in place of a failed snubber, then both the failed snubber (if it is repaired and installed in anothcr position) and the spare snubber shall be retested.

Test results of these snubbers may not be included for the re-sampling.

If any snubber selected for functional testing either fails to lockup o fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or desige deficiency all snubbers of the same design subject to the same t*fect shall be functionally tested.

This testi:.g requirement sha.1 be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For the snobber(s) found inoperable, an engineering evaluation shall be perform d on the components which are supported by the snubber (s).

The purp'se of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the design service.

=Permanent or other <.xemptions frcm functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemptfor is presented and/or snubber life destructive testing was performed to quam (y snubber operability for all design conditions at either the completion.,f their fabrication or at a subsequent date.

NORTH ANNA - UNIT 1 3/4 7-29a Amendment No. 33

.I PLANT SYSTEMS SURVEILLA CE REQUIREMENTS (Continued) d.

HydraulicSnubbersFunctionaUestAcceptanceCriteria The hydraulic snubber functional test shall verify that:

1.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement r'aall be verified.

e.

Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1.

The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.

Drag force shall not have increased more than 50% since the last functional test.

2.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

3.

Snubber release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required not to displace under continuous lead, the ability of the snubber to withstand load without displacement shall be verified.

f.

Snubber Service Life Monitoring A reccrd of the service life of each snubber, the date at which the designated service life commences and the installation and mainte-nance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.

At least once per 18 rnonths, the installation and maintenance records for each snubber 1.isted in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber NORTH ANNA - UNIT 1 3/4 7-29b Amendment No. 33

D PLANT SYSTEMS SURVEILEANCE REQUIREMENTS (Continued) service life review.

If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review.

This reevaluation, replacement or reconditioning shall be indicated in the. records.

c-NORTH ANNA - UNIT 1 3/4 7-29c Ameridment No. 33 O

TABLE 3.7-4a

(*

SAFETY RELATED HYDRAULIC SNUBBERS *'

E3 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY QJFFICULT No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REP 4VE j

(A or I)

(Yes or No)

~

2 Q

804 CH - 255-A I

Yes No 805 CH - 255-A I

Yes No 807 CH - 238-1 I

Yes Yes 808 CH - 238-1 I

tes Yes id 803 CH - 232-6 I

No Yes a

811 CH - 251 -12 I

Yes No 800 CH - 262-A I

Yes No 2I 801 CH - 252-A I

Yes No 54 k

810 CH - 263-12 I

Yes Yes

=

O 809 CH - 236-12 I

Yes Yes O

812 CH - 236-8 I

Yes Yes 813 CH 236-8 I

Yes Yes

TABLE 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

2 Z

x SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY OIFFICULT 5

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONF**

TO REh0VE

- (Yes or No)

(A or I)

(Yes or No)

E m

814 CH-251-C I

Yes No 802 CH-262-C I

Yes Yes 815 CH-235-C I

Yes Yes 859 CH-226-10 A

No No 860 CH-222-ll A

No No L

~

187 CH-244-12 I

Yes No 186 CH-244-12 I

Yes ilo E

E 185 CH-251 -12 I.

Yes Yes 842 CH-251-6 A

No No

!?

{

189 CH-244-Pent A.

No No w

190 CH-244-Pent A

No Yes 1 91 CH-244-Pent A

No No

'l Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

5 G

I SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGil RADIATI0il ESPECIALLY DIFFICULT' NO.

ON, LOCATION (ELEVATION-AREA) # INACCESSIBLE ZONE **

TO REMOVE y

(A or I)

(Yes or No)

E 188 CH-244-Pent A

No No 806 CH-251-A I

Yes No 203A QS-338-11 I

No Yes 2038 QS-338-11 I

No Yes 207 QS-267-11 A

No No 209A QS-338-2 I

No Yes 2098 QS-338-2 I

No Yes

[

600 QS-256-11 I

yes ye3 h

800 QS-274-QSH A

No No 801 QS-274-QSH A

No No

{

802 QS-272-QSil A

No No n

{

803 QS-270-QSH A

No No 804 QS-270-QSil A

tio No E

M M

f

eg TABLE 3.7-4a (Continued) g SAFETY RELATED HYDRAULIC SNUBBERS

S x

n SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT EE No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO RE50VE 7

(A or 1)

(Yes or No)

E U

100 RC-247-A I

Yes No 1 01 RC-246-A I

Yes No e

102 RC-234-18 I

No Yes R

u 7

w u>

1 04 RC-278-P I

Yes Yes 105 RC-278-P I

Yes Yes 106 RC-308-P I

Yes No 1 07 RC-308-P 1

Yes No M

h 108

'RC-232-9 3/4 I

No Yes 2

[

109 RC-235-6 I

Yes Yes

?

{;

110 RC-234-6 I.

Yes Yes 111 PC-2a7-C I

Yes No

-~

3 TABLE 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

2 h

SNUBBER SYSTEM SNUBBER INSTALLE0 ACCESSIBLE OR HIGH RADIATION ESPECIALLY.d FFICULT 2"

No.

ON, LOCATION (ELEVATION-AREA)# ~ INACCESSIBLE ZONE **

TO REMOVE (A or I)

(Yes or No)

(Yes or No) c-Q 112 RC-247-C I

Yes No 113 RC-259-P I

Yes Yes' ll4A RC-260-B I

Yes Yes 114B RC-258-P I

Yes Yes 3

u

?

ll5A RC-308-P I

Yes Yes ll5B RC-308-P I

Yes Yes y

ll6A RC-308-P I

Yes Yes a

ll6B RC-308-P I

Yes Yes 5

I gi 117 RC-308-P I

Yes No U

118 RC-308-P I

Yes No 119A RC-306-P I

Yes No 119B RC-306-P I

Yes No l

\\

i l

i TABLE 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS *

~

5!

SNUBBER SYSTLM SNUBBER Ii4 STALLED

. ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT g

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE g

(A or I)

(Yes or No)

(Yes or/No) i E

G 120 R C-310-P I

Yes No m

121 RC-302-P I

Yes Yes 122 RC-303-P I

Yes Yes 123 RC-303-P I

Yes Yes

((

124A RC.306-P I

Yes No 124B RC-306-P I

Yes No 125 RC-306-P I

Yes Yes p

126 RC-307-P I

Yes-No g

[

127 RC-307-P I

Yes No 5

g 128 RC-302-P J

Yes Yes El 129 RC-301-P I

Yes No 130 RC-302-P I

ies No

i Table 3.7-4 a (Continued)

!5 SAFETY RELATED HYDRAUL IC SNUBBERS

d x

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDIFFIbLT I;

No.

ON, LOCATION (ELFVATION-AREA)8 INACCESSIBLE ZONE **

TO RLMOVE (A or I)

(Yes or No)

=d

-i 131 A RC-306-P I

Yes No 131B RC-306-P I

Yes No 132 RC-307-P I

Yes No 133 RC-302-P I.,

Yes Yes

.2 y

134 RC-304-P I

Yes Yes 135 RC-304-P I

Yes Yes 136A RC-306-P I

Yes Yes 136B RC-306-P I

Yes No

,T 1

136C RC-306-P I

Yes Yes 137 RC-306-P I

Yes No

?

g; 450 CC-229 RCB I

Yes Yes u>

853 RC-256-A 1

Yes Yes 856 RC-256-A I

Yes Yes

i TABLE 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS *

~

Eifi SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RAD'ATION ESPECIALLY DIFFICULT

[

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE g;

(A or I)

(Yes or No)

(Yes or/No)

P I

847 RC-256-A I

Yes Yes a

848 RC-256-B I

Yes Yes 849 RC-256-C I

Yes Yes 852 RC-256-C I

Yes Yes 855 RC-256-C I

Yes Yes u,

2 y

854 RC-256-B I

Yes Yes d

851 RC-256-B I-Yes Yes 5"

858 RC-256-C I

Yes Yes

?

E 857 RC-256-B I

Yes Yes O

850 RC-235-A I

Yes Yes 817 RC-235-6 I

Yes Yes 818 RC-236-6 I

4es Yes I

.--.e

_n

i TABLE 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

is

~

ES SNUBBER SYSTEM SNllBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT

?;

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE No.

(A or I)

(Yes or No)

(Yes or/No) s i

C 55 821 R C - 238-18';,

I Yes Yes

--i a

822 RC-236-1 I

Yes Yes f

833 RC-243-B I

Yes Yes 826 RC-243-C I

Yes No a

827 RC-243-C I

Yes No v23;.

{

834 RC-243-B I

Yes No co 837 RC-244-A I

Yes No 3r 838 RC-244-A I

Yes No m

i g

842 RC-246-A I

Yes Yes 5

EF 843 RC-247-A I

Yes No.

u>

835 RC-243-B I

Yes No 839 RC-243-B I

Yes No

..-~

G.

l TABLE 3.7-4a (Continued) _

5 SAFETY RELATED HYDRAULIC SNUBBERS

5 5

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDi'FFICULT 5

No.

ON, LOC'ATION(ELEVATION-AREA)#_ INACCESSIBLE ZONE **

TO REMOVE (A or I)

(Yes or No)

(Yes or No) i 5

Z 840 RC-243-A I

Yes No 841 RC-243-A I

Yes Yes -

819 RC-236-A I

Yes Yes

~

s No 832 RC-243-B I

Yes w

w

=

s u

820 RC-736-17 I

Yes Yes g

N 831 RC-243-B I

Yes

-40 1

)

i

~ No p

823 RC-243-C I

Yes

[

824 RC-243-C I

Yes No S

g 860 RC-261-B I

Yes

'Yes 4

\\

w" 862 RC-261-B I

Yes

.Yes 864 RC-258-B I

Ygs

, '( Yes) '

~

C6S RC-258-B I

Yes Yes x

s.

\\

5 3

3 _ __ _

_ _ _.. ( _,.

~

1 s

\\

O

\\

h g

- i

'i %

g y

s i _,

1

$ [t 4

.3 q

TABLE 3.7-4c (Continued) 5 s

SAFETY RELATED HYORAULIC SNUBBERS

b 7

~

M SNUBBER SY5iEM SNUBBER ItiSTALLED

. ACCESSIBLE OR HIGH h.01ATION ESPECIALLY DIFFICULT

' No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE j

( A o, J )

(Yes or No)

(Yes or/No) c

=

Yes Yes 863 RC-260-B I

868 RC-258-B I

Yes Yes 4

828 RC-244-A I

Yes Yes 829 RC-244-A I

Yes Yes R

830 RC-244-A 1

I Yes No u

N 1.

861 RC-261-B I

Yes No o

869 RC-258-C I

Yes Yes k

880 RC-261-C I

Yes Yes a

871 RC-261-C I

Yes Yes

=

?

879 RC-258-C I

Yes Yes O

859 RC-256-B I

Yes Yes 866 RC-257-B I

fes Yes

e 1

TABLE 3.7-4a (Continued)

=

SAFETY RELATED fiYDRAULIC SNUBBERS

S2 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY D'IFFICULT EE No.

ON, LOCATION (ELEVATION-AREA)# INACCESSIBLE ZONE **

TO REMOVE j'

(A or I)

(Yes or No)

E G

870 RC-258-C I

Yes Yes 877 RC-263-C I

Yes Yes 876 RC-258-C I

Yes Yes 890 RC-258-A I

Yes Yes w

[*

878 RC-258-C I

Yes Yes E

~

882 RC-260-A I

Yes Yes 8 84 RC-261-A I

Yes Yes g.

3 889 RC-258-A I-Yes Yes

$n 872 RC-261-C I

Yes Yes

=

(j 887 RC-258-A I

Yes Yes g

886 RC-258-A I

res Yes 223 PC-258 A I

Yes Yes

'l Table 3.7-4a (Continued) 2 SAFETY RELATED HYDRAULIC SNUBBERS

85 SNUBBER SY', TEM SNUBBER INSTALLED ACCESSIB' 6 OR HIGil RADIATION ESPECIALLY/* DIFFICULT

>5 No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE' 3"

(A or I)

(Yes or No)

E G

883 RC-260-A I

Yes Yes s

885 RC-260-A I

Yes Yes 873 RC-262-C I

Yes Yes 875 RC-256-C I

Yes Yes

~

893 R C - 268-9',

I Yes No 889A RC-268-9'3 I

Yes No j

891 RC-260-C I

Yes Yes aj 890A R C-298-9',

I Yes Yes c+

Ei lilA RC-298-923 I

Yes No w"

892 RC-261-C I

Yes Yes 867 RC-258-B I

,Yes Yes

~

881 RC-258-A I

Yes Yes

3 Table 3.7-4a (Continued) 2 SAFETY RELATED HYDRAULIC SNUBBERS *

-d N

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECI ALLY DIFFICULT E

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE f"

(A or I)

(Yes or No)

Si a

100A RC-265-P I

Yes No

_o 101A RC-265-P I

Yes No -

102A RC-265-P I

Yes No 103A RC-265-P I

Yec No w

[

104A RC-264-A I

Yes Yes k

105A RC-264-A I

Yes Yes y

106A RC-264-8 I

Yes Yes m

S' 107A RC-264-B I

Yes Yes A

g 108A RC-264-C I

Yes Yes U$

109A RC-264-C I

Yes Yes 138 RC-238-9 3/4 I

No Yes 139 RC-252-ll I

Yes Yes

1 Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

jg S

x 2

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY pIFFICULT E

No.

ON, LOCATION (ELEVATION-AREA)# INACCESSIBLE ZONE **

TO REMOVE 2:

(A or I)

(Yes or No)

Ea 140 RC-245-11 I

Yes No 53-46 RC-249-A I

Yes No 53-46A RC-249-A I

Yes No 217-4 RC-243-B I

Yes Yes R

i 223-4 RC-303-P I

Yes No 5:

3g a-O O

e n.-

1

_able 3.7-4a (Continued)

T SAFETY RELATED HYDRAULIC SNUBBERSo.

8d SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE

[

(A or 1)

(Yes or No)

(Yes or/No) -

g 2-t

~

100A Ril-228-8 A

No No 100B RH-228-8 A

No No m

100C RH-228-8 A

No No' 1000 Ril-228-8 A

No No A

No No 100E Ril-228-8 2

y 101A Rii-228-5 A

No No 102A RH-228-5 A

No Yes 102B Ril-228-5 A

No Yes h

103A Ril-228-3 A

No Yes a

103B Ril-228-3 A

No Yes

?

g 103C Ril-228-3 A

No Yes 104A Ril-233-4 I

Ves No n

.,o

i

~

Table 3.7-4a (Continu-d)

SAFETY RELATED HYDRAULIC SNUBBERS

Es h

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIA1' ION ESPECIALLY DIFFICULT Nc.

ON, LOCATION (EL EVATION-AREA [#

INACCESSIBLE ZONE **

TO REMOVE 5

(A or.I)

(Yes or No)

(Yesorgb) 2 s

105A Ril-22 5-A I

No Yes 106A RH-24 4-4 I

Yes Yes 107A R H-22 9-3 A

ik.

Yes 1078 RH-22 9-3 A

No Yes A

No Yes 4d 107C R H-22 9-3 a

108A RH-237-2 A

No Yes m

108B R H-23 7-2 I

Yes Yes 109A RH-2 4 5-3 I

Yes Yes 109B Ril-245-3 I

Yes Yes m

5 109C RH-24 5-3 I

Yes Yes O

1090 R H-24 5-3 I

Yes Yes U

I Yps No 110A R H-24 G-93 I

Yes No 110B RH-24 0- 93 I

'l l

l Table 3.7-4a (Continued)

SAFETY RELATED llYDRAULIC SNUBBERS

S s'

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFIC0LT 3

NO.

ON, LOCATION (ELEVATION-ARLA) #

INACCESSIBLE ZONE **

TO REMOVE 55 (A or I)

(Yes or Ho)

E

[

110C Ril-240-5 I

Yes No 1100 Ril-240-5 I

Yes No 111A RH-227-4 I

Yes Yes 111B Ril-227-4 I

Yes Yes e

112A RH-224-4 I1 Yes Yes 113A Ril-224-4 I

Yes Yes w

1138 Ril-224-4 I

Yes Yes a

u 114A Ril-224-4 I

Yes No E

115A RH-234 I Yes Yes 116A RH-229-4 I

Yes Yes

[

117A Ril-224-4 I

Yes No I

118 Ril-224 -6 I

Yes Yes 119 Ril-240-5 I

Yes Yes 2f 452 Ril-234-7 I

Yes Yes O

i Table 3.7-4a (Continued)

SAFETYRELATEDHYDRAULICSNUBBERS*

2 3$

Sf0BBER SYSTEll SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY D'IFFICULT 3

35 No.

ON, LOCATION (ELEVATION-AREA)#

INACCE$SIBLE ZONE **

TO REK0VE (A or I)

(Yes or No)

E G

202 RS-267-16 I

No Yes

_a 204A RS-338-9 I

No Yes 204B RS-338-9 I

No Yes 205A RS-338-10 I

No Yes 22**

205B RS-338-10 I

No Yes

'?'

S 206A RS-338-2 I

No Yes 206B RS-338-2 I

No Yes 3r 208-A RS-33B-2 I

No Yes e

E 2

208-B RS-338-2 I

No Yes R

E 136A RS-305-P A

No No O

o

_ ~ _ _. _..., - _.

- = - <

'1 Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERSA 2

od SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT

[

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE g

(A or I)

(Yes or No)

(Yes or/No) a C

200 SilP-291-RCA I

No Yes

~

201A SHP-291-RCA I

No Yes 201B SHP-291-RCA I

No Yes 202A SHP-291-RCA I

No Yes 202B SHP-291-RCA I

No Yes lq 210 SHP-291-RCA I

No Yes t

a y

211A SHP-297-MSVH A

No Yes 211B SHP-297-MSVH A

No Yes 212A Slip-297-MSVH A

No Yes k

212B SHP-297-MSVH A

No Yes 213A SHP-297-MSVH A

No Yes 213B SHP-297-MSVH A

No Yes 230 SHP-29/-MSVH A

No No m

w 231 Slip-297-MSVH A

No No 232 SHP-297-MSVH A

No No 261 SHP-277-MSVH A

No Yes 262 SHP-282-MSVH A

No No

~

1 Table 3.7-4a (Continued) y SAFETY RELATED HYDRAULIC SNUBBERS *

$ SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFF,1 CULT

~

s No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE /

(A or I)

(Yes or No)

(Yes or No)~

e Em

" 263 SHP-307-MSVH A

No No e

264 SHP-307-MSVH A

No No a

265 SHP-307-MSVH A

No No 266 SHP-282-MSVH A

No No 267 SHP-307-MSVH A

No No 2

y 268 SHP-307-MSVH A

No No 8

269 SHP-282-MSVH A

No No 6" 233 SHP-282-MSVH A

No No g

i l

E 234 SHP-282-MSVH A

No No 2

P 236 SHP-282-MSVH A

No No O

235 SHP-297-MSVH A

No Na 237 SHP-297-MSVH A

No No I

4 w

s

-e.mm w.

4 o..

.-e=

m

-..-em~~

i

e 1

Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

g d

x SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT l

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVEt' (A or I)

(Yes or No)

(Yes or Not i

"=M

(

238 SilP-282-MSVH A

No No No No 462 SHP-297-MSVH A

452 SHP-297-MSVH A

No No 472 SHP-297-MSVil A

No No e

270 SilP-307-MSVil

'A No No

[

246 SitP-291 -TBM A

No Yes b

247 SHP-288-TBM A

No Yes 1

248 SilP-288-TBM A

No Yes E

k 249 SitP-27 3-TBM A

No No M

S 250' SitP-268-TBB A

No Yes E

251 SHP-287-TBM A

No Yes w

252 SHP-267-TBB A

No Yes

~..

~

q Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBER $*

S SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY QIFFICULT E

No.

ON, LOCATION (ELEVATION-AREA)# INACCESSIBLE ZONE **

TO REMOVE 5

(A or I)

(Yes or No)

(Yes or No) i E

[

253 SHP-267-TBB I

No Yes 254 SHP-267-TBB I

No Yes 255 SHP-277-TBM A

No Yes 256 SHP-274-TBB A

No Yes t

w 257 SHP-294-TBM A

No Yes to D

258 SHP-294-TBM A

No Yes Y

IO 259 SHP-294-TBM A

No Yes 260A SHP-277-MSH A

No No F

[

260B S11P-277-MSH A

No No 5

220A SHP-300-SB A'

No Yes' 6

5{

220B SHP-300-SB A

No No ta 221A SHP-300-SB A

No Yes e-e

.-e---.ee.--.

.-~,

Table 3.7-4a (Continued) 2 SAFETY RELATE 0 HYDRAULIC SNUBBERS

g y

t' SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR' HIGH RADIATION ESPECIAt!.Y DIFFICUt'T 3

25 NO.

ON, LOCATION (ELEVATION-AREA) # INACCESSIBLE ZONE **

TO REMOVE S

(A or I)

(Yos or No)

(Yes or No) e E

221, SilP-300-SB A

No No 222k SHP-300-SB A

No

.Yes 222B SHP-300-SB A

No No 224A SHP-300-SB A

No.

Yes e

224B SilP-300-SB A1 No Yes.

~

22SA SHP-300-SB A

No No 225B SHP-300-SB A

No No R

226 SHP-300-SB A

Oio No

?$

227A SilP-300-SB A

No No 227B SHP-300-SB A

No Yes 228A Slip-300-SB A

No No 2288 SHP-300-SB A

No No 5

229 SilP-300-SB A

No No zo O

1 Table 3.7-4a (Continued) y SAFETY RELATED HYDRAULIC SNUBBERS

2 g

SNUBBER SYSTEM SNUBBER' INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLhDIF'FICULT No. ~

ON, LO_ CATION (ELEVATION-AREA)# INACCESSIBLE ZONE **

_ (Yes or No)

TO REMOVE (A or I)

(Yes or No)

~

E Z

m 217A SHP-297-MSVH A

No Yes 217B SHP-297-MSVit A

No Yes 218A SilP-297-MSVH A

No Yes 218B SHP-297-MSVH A

No Yes w

2 i

219A SilP-297-MSVH A

No Yes y

Ei#

219B SHP-297-MSVH A

No Yes 209A Slip-291-RCA I

Yes Yes F

2093 SHP-291-RCA I

Yes Yes 223A SHP-291-RCA I

Yes Yes 1

223B SHP-291-RCA I

Yes Yes

~

23A SHP-290-MSVH A

No.

No 23B SHP-290-MSVH A

flo No o

k

gg Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

2 f,

gi SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO: REMOVE E

(A or I)

(Yes or No)

(Yes or No) s a

30A SHP-290-MSVH A

No No 30B SHP-290-MSVII A

No No 38A SHP-290-MSVH A

No No 38B SHP-290-MSVH A

No No y

203 SHP-291 -RCA I

Yes Yes m

E 204 SHP-291 -RCA I

Yes Yes 205 SHP-291-RCA I

Yes Yes 206 SHP-291-RCA I

Yes Yes g

207 SHP-291-RCA I

Yes Yes 1

208 SHP-291-RCA I

Yes Yes n

5 3

ti

8 g

Table 3.7-4a (Continued) __

h SAFETY RELATED HYDRAULIC SNUBBERS

b SNUBBER SYSTEM StiUBBER IfiSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDIFF{ CULT NO.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE,

(A or I)

(Yes or.No)

(Yes or No)'

>g q

400A SI-258-13 I

No Yes 4008 SI-258-13 I

No Yes 400C SI-258-13 I

No Yes 4000 SI-258-13 I

No Yes R

101A SI-256-SG

'A No No 1

?

101 B SI-256-SG A

No No 102A SI-256-SG A

No No 102B SI-256-SG A

No No 104A SI-256-SG A

No No i I 1

r9 EF

?

O O

d

)

<j Table 3.7-4a (Continued) 9 SAFETY RELATED HYDRAULIC SNUBBERS

2 E$

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT '

>5 No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO RENOVE 2'

(A or I)

(Yes or No)

E Z

104B SI-256-SG A

No No m

105 SI-256-SG A

No No 106 SI-256-SG A

No No l

100 SI-257-B A

No Yes l

w 1 01 SI-257-B I

No Yes 1

R l

[

1010 SI-237-3 I

No Yes m

101C SI-257-B I

No Yes 102C SI-221-B A

No No E

g 103A SI-238-C I

Yes Yes 103B SI-238-C I

Yes Yes 2

P 103C SI-238-C I

Yes Yes d

104 SI-221-C A

No No

1 1

Table 3.7-4a (Continued) 1 j

SAFETY RELATED HYDRAULIC SNUBBERS

E g

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDIFFICdLT 3;

NO.

ON, LOCATION (ELEVATION-AREA) # INACCESSIBLE ZONE **

TO REMOVE j

(A or I)

(Yes or No)

(Yes or No) l E

H 105A SI-238-A I

No Yes l

~

i 105B SI-238-A I

No Yes I

105C SI-238-A I

No Yes

)

106A SI-221-A A

No No 107 SI-256-SG A

No No I

108 SI-256-SG A,

No No j

109 SI-250-A I

Yes No l

110 51-219-A A

No No I

111 SI-241-1 A

No No w

j i

112 SI-256-SG A

No No

}

7 113 SI-256-SG A

No No w

i 451 SI-238-9 I

Yes Yes 700 SI-256-SG A

No No 1

701 SI-256-SG A

No No l

,g y

s 702' SI-256-SG A

,No No 703 SI-256-SG A

No No

,o 5

i E

9 i

n 1

I k

1 r

~

Q Table 3.7-4a (Continued) l' SAFETY RELATED HYDRAULIC SNUBBERS *'

5 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT 2

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REM #/E jf:.

(A or I)

(Yes or No)

(Yes or No) i si ff 200 WFPD-291-RCA A

No No 201 WFPD-291-RCA A

No No 202 WFPD-291-RCA A

No No 203 WFPD-291-RCA A

No No 204 WFPD-291-RCA A

No No

?

S]

205 WFPD-291-RCA A

No Yes 206 WFPD-291-RCA A

No No 207 WFPD-291-RCA A

No No h-208 WFPD-291-RCA A

No No E

<+

209 WFPD-291-RCA A

No No

=

210 WFPD-291-RCA A

No No 211 WFPD-291-RCA A

No No

o 1

g Table 3.7-4a (Continued) m SAFETY RELATED HYDRAULIC SNUBBERS

Eg SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDIFF{ CULT ND.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE, (A or I)

(Yes or No)

(Yes or No) c 5.

--4

~

212 WFPD-291-liCA A

No Nc, 21 6 WFPD-282-MSVli A

No No 217 WFPD-282-MSVH A

No No 21 8 WFPD-282-MSVH A

No No R

222 WFPD-272-MSVH A

No No E

223 WFPD-272-MSVH A

No No 224 WFPD-272-MSVH A

No No 231 A WFPD-291-RCA A

No Yes g

O "w

S 9

e

--e=

Q Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS

S i.

-4 SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE bR HIGH RADIATION ESPECIALLY DIFFIdULT

HO.

ON, LOCATION (ELEVATION-AREA) # INACCESSIBLE ZONE **

TO REMOVE S

(A or I)

(Yes or No)

E 231B WFPD-291-RCA A

No Yes 231C WFPD-291-RCA A

No Yes 231D WFPD-291-RCA A

No Yt s 235 WFPD-291-RCA A

No No a

600 WFPD-291-3 f

Yes No M

o 8

C a

R 2n f

~

4

~~..

1 h

Table 3.7-4a (Continued) m

)

SAFETY RELATED HYDRAULIC SNUBBERS

259

/.

8 SNUBBER SYSTEM SNUB 5ER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT g

NO.

ON, LOCATION (ELEVATION-AREA) #

INACCESSIBLE ZONE **

TO REMOVE q

(A or I)

(Yes or No)

(Yes or No) 213 FW-300-SB A

No No L

214 FW-300-SB A

No No 215 FW-300-SB A

No No 226A FW-300-SB A

No No m

N

]

226B FW-300-SB A

No No b

227A FW-300-SB A

No No 2278 FW-300-SC A

No No 228 FW-300-SB A

No No 229 FW-300-SB A

No No k

230 FW-300-SB A

No No' t

=

81

?

e a

e e

i 2

~

k Table 3.7-4a (Continued) r

< 2r SAFETY RELATED HYDRAULIC SNUBBERS

g

. 4-SNUBBER SYSTEM SNUBBER INSTALLED' ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT E5 NO.

ON, LOCATION (ELEVATION-AREA) #

INACCESSIBLE ZONE **

TO REMOVE El (A or I)

(Yes or No)

(Yes or No) 245A FW-295-FWH A

No Yes I

245B FW-295-FWH A

No Yes 246 FW-295-FWH A

No Yes 4

g 233 SDHV-307-MSVH A

No No b2 233A SDHV-307-MSVH A

No No 234 SDHV-307-MSVH A

No No 235 SDHV-307-MSVH A

No Yes 236 SDHV-297-MSVH A

No No 2o1 R

o.

3 3

Table 3.7-4a (Continued) l SAFETY RELATED HYDRAULIC SNUBBERS

5 SNUBBER SYSTLM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATICi:

ESPECIALLY DIFFICULT R

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REM 6VE (A or I)

(Yes or No)

(Yes or No) i E

200 WS-256-SG A

No No 201 WS-256-$G A

No No 202 WS-244-ABB A

No No' 203 WS-244-ABB A

No No 204A WS-244-ABB A

No No

?

R 2048 WS-244-ABB A

No Yes 206 WS-244-ABB A

No No F

207 WS-244-ABB A

No No m

208 WS-244-ABB A

No No 5

,5 20SA WS-244-ABB A

No No U

2058 WS-244-ABB A

No Yes e

e e

i 2

Table 3.7-4a (Continued)

R SAFETY RELATED NYDRAULIC SNUBBERS

x E

l, x

SNUB 8ER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT HO.

ON, LOCATION (ELEVATION-AREA) # INACCESSIBLE ZONE **

.TO REMOVE E

(A o-1)

(Yes or No)

Q a

t 405 CC-224-Pent A

No Yes 407 CC-224-Pent A

.No No E

a 7

m 411 CC-255-Pent A

No No 412 CC-252-Pent A

No No 413 CC-256-Pent A

No No p'

k 202 FC-249-FBB I

No No

?s 204 FC-249-FBB I

No No 5

W W

~

3

[

Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS *.

5 El SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT 3:

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE 3E (A or 1)

(Yes or No)

(Yes or.No) si 1

C 25 1

WGCB-246-A I

Yes Yes

-4

~

2 WGCB-246-C I

Yes Yes lA WGCB-244-Pent I

Yes No 2A WGCB-244-Pent I

Yes fo I

No Yes 103 WGCB-279-TBM j

104 W3CB-279-TBM I

No Yes w2 7

i 2

.T 1

L R

E E

y O

4

o 1

Table 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS **

2 S

w I

SNUBBER SYSTEM StUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT 5"

No.

ON, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REM,0VE 5

(A or I)

(Yes or No)

E 237 SAE-307-MSVit A

No No 238 SAE-307-MSVH A

No No

's 239 SAE-307-MSVH A

No No s

240 SAE-307-MSVH A

No No i

w

,241 SAE-307-hSVil A

No No w2 242 SAE-307-MSVil A'

No~

No s

s i

y 1

243 SAE-297-MSVH A

No No g,-

244 SAE-297-MSVil A

No No E

to R

245 SAE-297-MSVli A

No No 1

g s-g g

~-

e

~ '

t v

6

?w se e

m

>h-g T

A

i Table 3.7-4a (Continued) 5 SAFETY RELATED HYDRAULIC SNUR9ERS*

x 3

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDIFFICdLT s

No.

nN, LOCATION (ELEVATION-AREA)#

INACCESSIBLE ZONE **

TO REMOVE (A or I)

(Yes or No)

(Yes or No) s

=

5 a

2a6 SAE-274-AF9 A

No No P.47 SAE-297-AFH A

No No 248 SAE-207-AFW A

No No 249 SAE-297-AFN A

No No No 250 SAE-207-AFW A

No g

s

[

2 51 SAE-207-AFH A

No No

[

252 SAE-297-AFW A

No No 253 SAE-207-AFH A

No No 254 SAE-297-AFN A

No No 255 SAE-297-AFM A

No No 256 SAE-207-AFW A

No No k

257 SAE-247-AFM A

No No 5

e O

+

1 Table 3.7 Aa (Continued) 5 SAFETY RELATED HYORAllLIC SNUBBERS

Q E

SNUBBER SYSTEM SNURRER INSTALLE0 ACCESSIBLE OR~

HIGH RADIATION ESPECIALLY DItTICilCT

~ r No.

ON, LOCATION (ELEVATION-AREA)# ' INACCESSIBLE 7.ONE*

TO REMOVE

/

(A or I)

(Yes or No)

(Yes or No) i b

a 280 SAE-305-MSVH A

No Yes 281 SAE-305-MSVH A

No Yes 282 SAE-305 hSVH A

No Yes t

7 2

e a

R an O.

S e

a

0 Table 3.7-4b SAFETY RELATED MECHANICAL SNUBBERS

2 58 SHUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLYDIFFICULT~

25 NO.

ON, LOCATION (ELEVATION-AREA) # INACCESSIBLE ZONE **

TO REMOVE 5-(A or I)

(Yes or No)

E A

118 CFPD-304-3 i

Yes No 119 CFPD-304-3 I

Yes No 221 CFPD-304-13 I

Yes No 224 CFPD-304-13 I

Yes No E

I a

N o

\\

.I

![

g it an O.

s J

e O

m

.w.

TABLES 3.7-4a AND 3.7-4b (Continued)

TABLE NOTATIONS

LOCATION ABBREVIATIONS Abbreviations Area A

Cubicle A B

Cubicle B C

Cubicits C Pent.

Penetration Area Aux. Bldg.

P Pressurizer Cubicle RCA Reactor Containment Annulus MSVH Main Steam Valve House MSH Main Steam Header - Turo. Bldg.

TBM Turbine Bldg. Mezzanine TBB Turbine Bldg. Basement SB Service Bldg.

SG Safeguards Bldg.

FWH Feedwater Header - Turb. Bldg.

ABB Auxiliary Bldg. Basement FSB Fuel Bldg. Basement AFW Auxiliary Feedwater Pump House NOTE:

Numbers indicate radial locations in reactor containment.

Snubbers may be added to and deleted from safety related systems without prior

~

License Amendment to Tables 3.7-4a and 3.7-4b provided that a revision to Tables 3.7-4a and 3.7-4b is included with the next License An.endment request.

- Modifications to this table due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Tables 3.7-4a 3.7-4b is included with the next License Amendment erquest.

NORTH ANNA - UNIT 1 3/4 7-66 Amendment No. 33

b PLANT SYSTEMS o

i BASES t

i 3/4.7.5 ULTIMATE HFAT SINK i

The limitations on the ultimate heat sink level and temperature j

ensure that sufficient cooling capacity is available to either 1) pro-vide normal ~ cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is con-sistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants", March 1974.

3/4.7.6 FLOOD PROTECTION The limitation on flood protection ensures that facility protective j

actions will be taken (and operation will be terminated) in the event of

.I flood conditions. The limit of elevation 256 feet Mean Sea Level USGS datum is based on the maximum elevation at which facility flood control measures provide protection to safety related equipment.

3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS The OPERABILITY of the control room ventilation system ensures that

1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instru;rentation cooled by this system and 2) the control room will remain habitable for opera-tions personnel during and following all credible accident conditions.

The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equiva-lent.

This limitation is consistent with the requirements of General Design Criteria 19 of Appenoix "A",10~ CFR 50.

3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM The OPERABILITY of the safeguards area ventilation system ensures that radioactive materials leaking from the ECCS equipment within the pump room following a LOCA are filtered prior to reaching the environ-ment.

The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses.

NORTH ANNA - UNIT 1 B 3/4 7-5

PLANT SYSTEMS BASES 3/4.7.9.1 AND 3/4.7.9.2 RESIDUAL HEAT REMOVAL SYSTEM (RHR)

The OPERABILITY of the RHR system ensures that residual heat removal capability is available below 350*F following plant shutdown.

The RHR system is not part of the ECCS system.

3/4.7.10 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of-the reactor coolant system and all other safety related systems is maintained during and following a seismic or other even't initiating dynamic loads.

Snubbers excluded from this inspection program are those installed on nunsafety-related systems and then only if their failure or failure of the system on which they are installed,.would have no adverse effect on any safety-related system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval. varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspecticn.

However, the results of such early inspections performed before the original required time intervtl has elapsed (nominal time less 25%) may not be used to lengthen the required inspection' interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.

Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

When a snubber is found inoperable, an engineering evaluation is perYormed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber.

The engineering evaluation

C~

shall determine whether or not-the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutcowns at 18 months intervals.

Observed failures of these sample snubbers shall require functional testing of additional units.

NORTH ANNA - UNIT 1 B 3/4 7-6 Amendment'No. 33

A PLANT'4YSTEMS 3

BASES 1

The service life of a snubber is evaluated via manufacturer input and l

information~through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replacad, in high radiation area, in high temperature area, etc...).

The requirement'to monitor the snubber service life is included to l

ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical i

~

bases for future consideration of snubber service life.

The requirements for the maintenance of records and the snubber service life review are not -

intended to affact plant operation.

3/4.7.11' SEALED SOURCE CONTAMINATION The limitations on sealed source renovable contemination ensure that the total,txxh/ or individual organ irradiation does not sxceed allowable limits in the event of ingestion or inhalation of the source material.

The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.33(c) limits for plutonium.

Leakage of sources excluded fro.m the requirements of this specification represent less than one maximum permissible body burden for total body irradiation if the source material is inhaled or ingested.

Sealed sourtes are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group. Those sources which

are frequently handled are required to be tested more often than those i

which are not.

Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be 4

tested unless they are removed from the shielded mechanism.

1 i

r NORTH ANNA - UNIT 1 8 3/4 7-7 Amendmen't No. 72, Jg. 33

PLANT. SYSTEMS s.

i BASES ~

i 3/4.7.12 SETTLEMENT OF CLA5] 1 STRUCTURES I

In order to assure that settlement does not exceed predicted and allowable. settlement values, a program has been established to conduct a survey of a specified number of points at the site on a semi-annual basis. The first survey was conducted in May 1976 to establish base-I line elevations for most of the points. Where applicable, the base-line elevations of points established subsequent to the May 1976 survey have been adjusted to the May 1976 survey by an evaluation of the settlement records of settlement points on the same structure or on nearby struc-i tures.

Baseline elevations for some points were established on dates otherthanMay1976asindicateginTable3.7-5. Additional surveys will be perfomed semiannually.

The determination of the elevation of the points shall be by precise leveling with second order Class II accu-racy as defined by the U. S. Department of Commerce, National Oceanic and Atmospheric Admic.istration, National Ocean Survey,1974. When any settlement point listed in Table 3.7-5 is inaccessible during a survey, comparison to allowable settlement shall be based on settlement of other points on the same structure or on' nearby structures having similar foundation conditions. When any settlement point listed in Table 3.7-5 is dislocated or replaced, a documented review of the settlement records of points on the same structure and additionally points on nearby structures having similar foundation conditions shall provide a new reference elevation for the point that reflectc tha estimated settlement since the base-line survey.

If the total settle-ment or differential settlement exceeds 75 percent of the ailowable value, the frequency of surveillance shall be increased as dictated by the engineering review.

i Allowable differential movement is controlled by pipe deflections permitted by fixation points in buildings.

The items limiting differen-l tial settlement are as follows:

l l

i em L

NORTH ANNA - UNIT 1 B 3/4 7-7a Amendment No. 16 l

(

ADMINI'STRATIVE CONTROLS

~.

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

~

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (a) receipt of an operating license, (?) amendment to

' the license involving a planned increase in power level, (3)- installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraalic 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 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 requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following comple-tion of the startup test program, (2) 90 days following resumption or commence-ment of commercial power operation, or (3) 9 months following initia1 criticality; whichever is earliest.

If the Startup Report does not cover all three events (i.e., 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 all three events have been completed.

4" 6

Amendment _.No. /B 77, 33 NORTH ANNA - UNIT 1 6-14

~

ADMINISTRATIVE CONTROLS a.

Recoros 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 facility radiation and contamination surveys.-

d.

" Records of radiation exposure for all individuals entering radiation control areas.

e.

Records of gaseous ~and liquid radioactive material released to

the environs.

f.

Records of transient operational cycles for those facility components identified in Table 5.9-1.

g.

Records of reactor tests and experiments.

h.

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

1.

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

j.

Records of Quality Assurance activities required by the QA Manual.

k.

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

CFR 50.59.

1.

Records of meetings of the SNSOC.

m.

Records of meetings of the System Nuclear Safety and Operating Committee to issuance of Amendment No. 30.

n.

. Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the date at which the service life ccmmences and associated installation and maintenance records.

y-c.

Records of secondary water sampling and water quality.

p.

Records of Environm' ental Qualification which are covered under the provisions of paragraph 6.13.

6-21 Amendment No. E,33 NORTH ANNA-UNIT 1 y

og D-

\\

ADMINISTRATIVE CONTROLS.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared con-sistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radia-tion 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 10 CFR 20, 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.

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 le made after the dose rate level in the area has been established and personnel have been made knowledgeable 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 perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.

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 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 Supervisor on duty and/or the Plant Health Physicist.

. e-

" Health Physics personnel snall 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.

NORTH ANNA - UNIT 1 6-22 Amendment No, M, 33

Neqvq[o

~

.j g

UNITED STATES E

NUCLEAR REGULATORY COMMISSION n

WASHINGTON, D. C. 20555 4.g.

,o b,,

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-339 NORTH ANNA' POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.13 -

License No. NPF-7

^

1.

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

A.

The application for amendment by Virginia Electric and' Power Company (the licensee) dated July 1,1981 as supplemented by letter dated September 10, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in "confonnity with the application,

- the provisions of the Act, and the rules and regulations of the Commission; C.

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

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

e~

2-

~..

~

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,- and paragraph 2.C.(2) Jof Facility Operating License No. NPF-7 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications conthined in~ Appendices 2

A and B, as revised through Amendmer.t No.13, are hereby incorporated in the license. The licensee shall operate the facilita in accordance with the Technical Specifications.

- 3.

This license amendment is effective on November 20, 1981.

FOR THE NUCLEAR REGULATORY COMMISSION Robert A. Clark, Chief Operating Reactors' Branch #3' Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: November 5, 1981 b

s

4 ATTACHMENT TO LICENSE AMENDMENT-kRENDMENTNO. 13 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified

- by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Pages 3/4-~7-26a7 3/4.7-25 _'

3/4 7-26b

-- ~

3/4~7-26c;-

?

3/4~7-26d:

-3 3/4 7-48a 3/4-7-49 B 3/4 7-6 B-3/4 7-6a 6-19 w

O 6

eg, -

e o

e

PLANT SY. STEMS

~,.

3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.10 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.

l

~ APPLICABILITY: MODES 1, 2, 3 and 4.

(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTION:

With one or.more snubbers inoperable, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months replace or restore,the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.10.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.

SURVEILLANCE REQUIREMENTS 9

4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.

a.

Visual Inspections The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.

If less than two (2) snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months i 25% from the date of the first inspection. Otherwise, subsequent visual inspections shall be performed in accordance with the folicwing schedule:

Subsequenc Visual ho. Inoperable Snubbers Inspection Period *g per Inspection Period 0

18 montns 1 25%

1 12 months 25%

2 6 months

25%

3,4 124 days 25%

5,6,7 62 days i 25%

8 or more 31 days i 25%

r-The snubbers may-be categorized-into two groups: Those accessible and those inaccessi',le during reactor operation.

Each group may be inspected independently in accordance with the above schedule.

The inspection interval sha'l not be lenthened more than one step at a time.

g The provisions of Specifiestion 4.0.2 are not applicable.

1 NORTH ANNA - UNIT 2 3/4 7-25 Amendment No.13

. - - i

~

PLANT SYSTEMS SURVEILLANC'E REQUIREMENTS (Continued) b.

Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visual indica-tions of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in these locations where snubber movement can be manually induced'without disconnecting the snubber,,that the snubber has freedom of movement and is not frozen up.

Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for t5e purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedled for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally l

tested in the as found condition and determined OPERABLE per Specifi-cations 4.7.10.d and 4.7.10.e.

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

All snubbers connected to an inoperable common hydraulic fluid reservior shall be counted as inoperable. snubbers.

c.

Functional Tests At least once per 18 months during shutdown, a representative sa ple of that number of snubbers which follows the expression 35 [1 +

],

where c=2 is the allowable number of snubbers not meeting the acceptance criteria selected by.the operator, shall be functionally tested either in place or in a bench test.

For each number'of snubbers above c which does not meet the functional test acceptance criteria of Specification 4.7.10.d or 4.7.10.e, an additional sample selectedaccordingtotheexpression35(1+[){c+1 (a - c) shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative i

.sampl e.

Functional testing shall continue according to the expression b[35(1+{)2]wherebisthenumberofsnubbetsfound y-inoperable in the previous re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested.

NORTH ANNA - UNIT 2 3/4 7-26a Amendment No. 13

1 PLANT SYSTEMS

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SURVEILLAhCE REQUIREMENTS (Continued)

The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and, capacity of snubbers.

At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

1.

The first snubber away from each reactor vessel nozzle 2.

Snub'ers within 5 feet of heavy equipment (valve, pump, turoine, notor, etc. ).

3.

Snubbers within 10 feet of the discharge from a safety relief valve.

Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in'"High Radiation Zones During Shutdown" shall also be included in the representative sample." Tables 3.7-4a and 3.7-4b may be ust.d join'ly or separately as the basis for the sampling plan.

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.

Test results of these snubbers may not be included for the re-sampling.

If any snubber selected for functional testing either fails to lockup or f ails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the sam defect shall be functionally tested.

This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snLbber(s).

The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable uf meeting the design service, e-

Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exenption is presented and/or snubber life destructive testing was performed to. qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.

NORTH ANNA - UNIT 2 3/4 7-26b Amendren No.13

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1.

Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

e.

Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:

1.

The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.

Drag force shall not have increased more than 50% since the las) functional test.

2.

Activation (restraining action) ic achieved within the specified range of velocity or acceleration in both tension and compression.

a' 3.

Snubber release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required not to displace under continuous load, the ability of

~

the snubber to withstand lead without displacement shall be verified.

f.

Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life comences and the installation and mainte-nance records on which the designated service life is based shall be maintained as required by Spec ~ " ation 6.10.2.

P At least once per 18 months, the installation andnmaintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber i

NORTH ANNA - UNIT 2 3/4 7-26c Amendment No. 13 I

'[

-- n 1

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) service life review.

If the indicateci service life will be exceeded prior to the next s'cheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so. as to. extend its service life beyond the date of the next scheduled service life review. This reevaluation, JP

,yeplacement or reconditioning shall be' indicated in the r'ecords.' ~

~

1

.?

i v~

NORTH ANNA - UNIT 2 3/4 7-26d Amendment No. 13

i-zg TABLE 3.7-4b g

SAFETY REdTED M'iCHANICAL SNUBBERS

u

~i E

HIGH RADIATION.

SNUBBER SYSTEM SNUBBER INSTAL'.ED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT E

NO.

ON, LOCATION AND ELEVATION INACCESSIBLE DURING SHUTDOWN"*

TO REMOVE (A or I)

(Yes or No)

(Yes or No) 1-t i

4 b

R ee 1.

}

7' e

i

. i 2it

.i a~

g

. TABLES 3.7-4a AND 3.7-4b (Continued)

~.

TABLE NOTATIONS

LOCATION' ABBREVIATIONS Abbreviations Area A

Cubicle A B

Cubicle B

.C Cubicle C Pent.

Penetration Area Aux. Bldg.

P Pressurizer Cubicle RCA Reactor Containment Annulus RCB Reactor Containment Basement RCP Reactor Containment Penetration Area MSVH Hain Steam Valve House AFPH Aux. Feedwater Pu.mp House MSH Main Steam Header - Turb. Bldg.

TBM Turbine B1dg. Mezzanine TBB Turbine Bldg. Basement SB Service Bldg.

SG Safeguards Bldg.

QS' Quench Spray Area FWH Feedwater Header - Turb. Bldg.

ABB Auxiliary Bldg. Basement y

FBB Fuel Bldg. Basement Residual Heat Removal Mezzanine

'RHR NOTE:

Numbers indicate radial location in reactor containment.

Snubbers may be added to and deleted trcm safety related systems without prior License Amendment to Tables 3.7-4a and 3.7-4b provided that a revision te Tables 3.7-43 and 3.7-4b is included with the next License Amendment request.

- Modifications to this table due to changes in high radiation areas may be made without prior License Amendment provided that a revisicn to Tables 3.7-4a i

and 3.7-4b is included with the next License Amendment request.

i i:

j e-NORTH ANNA - UNIT 2 3/4 7-49 Amendment No.13 i

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This page intentionally left blank.

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i NORTH ANNA - UNIT 2 3/4 7-50

s.

PLANT SYSTEMS

~.

BASES 3/4.7.5 ULTIMATE HEAT SINK The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) mitigate.the effects of accident conditions within acceptable limits.

The limitations on minimum wa'ter level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis tenperature and is consistent with the recommends-tions of Regulatory Guide 1,27, " Ultimate Heat Sink for Nuclear Plants",

March 1974.

3/4.7.6 FLOOD PROTECTION The limitation on flood protection ensures that facility protective actions will be taken (and operation will be terminated) in the event of flood conditions.

The limit of elevation 256 feet Mean Sea Level USGS datum is based on the maximum elevation at which facility flood control. measures provide protection to safety related equipment.

w 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS The OPERABILITY of the control room ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for contin-uous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

The OPERABILITY of this system in conjunction with control roca design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.

Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

Th.is limitation is consistent with the requirements of General Design Criteria 19 to Appendix

" A",10 CFR 50.

3/4.7.8 SAFEGUARDT AREA VENTILATION SYSTEft c-The OPERABILITY of t9e safeguards area ventilation system ensures that radioactive materials leaking from the ECCS equip 1ent within the pump room following a LOCA are filtered prior to reaching the environment.

Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months over a 31 day period is sufficient to reduce the buildup of. moisture on the adsorbers ani HEPA filters.

The operation of this system and the resultant effect on cffsite dosage calculations was assumed in the accident analyses.

NORTH ANNA - UNIT 2 B 3/4 7-5

PLANT SYSTEMS BASES 3/4.7.9.1 AND 3/4.7.9.2 RESIDUAL HEAT REMOVAL SYSTEM (RHR)

The OPERABILITY of the RHR system ensures that residual heat removal capability is available below 350*F following. plant shutdown.

The RHR system is not part of the ECCS system.

3/4.7.10 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic

^ loads.

Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible and verified by ir.sorvice functional testing, that snubber may be exempted from being counted as inoperabic.

Generically asceptible snubbers are those which are of a specific make or nodel and have the same dasign features directly related to rejection of the snubber by' visual inspection, or are similarly located or exposed to the same environmental conditions such as l

temperature, radiation, and vibration.

When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber made of failure, in i

order to determir,e if any safety-related component or system has bun adversely affected by the inoperability of the snubber.

The engineering evaluation y-shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

l To provide assurance of snubber functional reliability, a representative l

sample of the installed snubbers will be functionally tested during plant shutdowns at 18 months intervals. Observed failures of these sample snubbers l

i shall require functional testing of additional units.

4 NORTH ANNA.- UNIT 2 B 3/4 7-6 Amendment No. 13

{

l

.)

PLANT 3YSTEMS BASES The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubber, seal replaced, spring replaced, in high ' radiation area, in high temperature area, etc...).

The requirement to monitor.the snubber service life is'fncluded to ensure that the snubbers periodical,1y und;cgo a performance evaluation in view of their age and operating conditions.

These records will provide statistical bases for future consideration of snub.ber service life.

The requirements for the maintenance of records and the snubber service life review are not,

intended to affect plant operation.

=.

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.g NORTH ANNA - UNIT 2 B 3/4 7-6a Amendment tio. 13

e ADMINISTRATIVE CONTROLS c.

Each REPORTABLE OtCURRENCE submitted to the Commission.

d.

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

e.

Records of changes made to Operating Procedures, f.

.. Records of radioactive shipments, g.

Records of sealed source leak tests and results.

h.

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 modifications 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.

Recordsoffacilityradiatioilandcontaminationsurveys.

c.

d.

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

e.

Records,of gaseous and liquid radioactive material release to the environs.

f.

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

g.

Records of reactor tests and experiments.

h.

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

i.

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

v-j.

Records of Quality Assurance activities required by the QA Manual.

k.

Records of the service life of all hydraulic and mechanical snubbers listed on Tables 3.7-4a and 3.7-4b including the date at which the i

service life commences and associated installation and maintenance 4

records.

NORTH ANNA UNIT 2 6-19 Amendment No. 13

ADMINISTRATIVE CONTROLS

~.

1.

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

m.

Records of meetings of the SNSOC.

n.

Recceds of meetings of the System Nuclear Safety and Operating Committee to issuance of Amendment No.

o.

Records of secondary water sampling and water quality.

p.

Records for Environmental Qualification which are covered undhr the l

provisions of Paragraph 2.C(4)(e) of License No. NPF-7.

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 10 CFR 20,.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.

A radiation monitoring device which continuously indicates the radiation dose ; ate 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 l

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

c.

An individual qualified in the 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 perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the i

l Radiation Work Permit.

l

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of l

their assigned radiation protection duties, provided they comply with approved l

radiation protection procedures for entry in high radiation areas.

l l

Ofd6f dH66 MitMff 7, Inp NORTH ANNA-UNIT 2 6-20 Amendment No, 11

ML20033C426

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