NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106

Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106

ML20246F202
Person / Time
Site:	Rancho Seco
Issue date:	07/06/1989
From:	Crunk S SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NL-89-547, NUDOCS 8907130154
Download: ML20246F202 (25)

Text

,

t,Mt)suun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.o. Box 15830. Sacramento CA 95852-1830,(916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA NL 89-547 Tuly 6, 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Hashington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 AMENDMENT NO. 110 TO FACILITY OPERATING LICENSE NO. DPR-54 Attention: George Knighton The District received the subject document via NRC letter dated June 9, 1989.

The following discrepancy in the amended Technical Specification pages was noted:

Technical Specification Page x (Table of Contents) does not reflect the changes approved in Amendment No.106.

This discrepancy was discussed with Mr. Steve Reynolds of your staff on June 30, 1989.

Attached is a copy of Amendment No. 110 as issued by the District to controlled Technical Specifications Manual copyholders.

I Members of your staff with questions requiring additional information or clarification may contact Mr. Jeff Robertson at (209) 333-2935, extension 4918.

Sincerely, b,, Ynu Steve L. Crunk Manager Nuclear Licensing cc w/atch: S. Reynolds, NRC, Rockville J. B. Martin, NRC, Halnut Creek A. D' Angelo, NRC, Rancho Seco Aoolt

\

~

8907130104 890706 PDR ADOCK 05000312 P FDC RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799;(2o9) 333 2935 L- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ . _

i L .

l- ,

(5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate. such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be. deemed to contain and is subject to the conditions Chapter I: specified in the following Commission regulations in 10 CFR Part 20, Section 30.34 of Part 30 Section 40.41 of Part 40, Sections 50-ST~ind 50.59 of Part 50, and Section 70.32 of Part 70 is subject to all applicable provisions of the Act and to the rules c

regulations, and ordena of the Commission now or hereafter in effect; ,

and is below: subject to the additional conditions specified or incorporated (1) Maximum Powat The licensee is authorized to operate the facility at a steady ss te reactor core power level not in excess of 2772 megawatts thermal.  !

(2) Technical Specifications The Technical revised throu Specifications contained in Appendices A ,and as B

the license. gh Amendment No. 110, are hereby incorporated in accordance with the Technical Specifications.The licensee shall (Amendment 110 - 6/9/89)

(3) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard including amendments made pursuant to provisions o Miscellaneous Amendments and Search Requirements revisions to 10 CFR 50.90 and 10 CFR 50.54(p).10 CFR 73.55 (51 FR 27 Plan is incorporated into the Physical Security Plan.TheThe Safeguard Con plans, which contain Safeguards Inforniation protected under 10 CFR 73.21. ha= entitled:

Station Physical Security Plan," with revisions submitted" Rancho Se through December 14, 1987; Station Guard Training and Qualification Plan," with revisionsand submitted through August 2, 1982.

with 10 CFR 73.55 shall be implemented in accordance with theChan schedule set forth therein.

(Amendment 108 - 6/5/89)

, l'

. . .. j

-4 (4) The licensee may proceed with and is required to complete'the-modifications identified in Paragraphs 3.1.1 through 3.1.40 of the NRC's Fire Protection Safety Evaluation (SE) on the facility dated February 28, 1978, as amended June 20, 1989.and supplements thereto. .These modifications shall be completed as ,

sgecified ijnable 3.1 of the SE or supplements thereto. In addition,7he licensee shall submit the additional information identified in Table 3.2 of this SE in accordance with the schedule contained therein. In the event these dates for submittal cannot be met, the licensee shall submit a report, explaining the circumstances, together with a revised schedule.

(Amendment 111~- 6/20/89)

(5) The licensee shall perform the supplementary inservice tests and inspections of Nuclear Class 2 and Class 3 systems and components committed to in the letter of February 27, 1978, from J. J. Mattimoe to R. H. Reid.

(Amendment 20 - 5/30/78)

(6) In accordance with the provisions of 10 CFR 50.12(a) an exemption from the provisions of 10 CFR 50.55a(g)(4)(v) is granted, and the effective date for the start of the next 40-month period is extended from August 18,'1978 to October 18, 1979.

(Amendment 20 - 5/30/78)

(7) Systems Inteority 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 i icw as practical levels. This program shall include the i following: 1

1. Provisions ~ establishing preventive maintenance and periodic visual inspection requirements, and

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

(Amendment 31 - 3/27/81)

=

1 RANCHO SECO TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES AS OF 06/29/89 APPENDIX A PACE NLHBER AMENDMENT NLHBER 1 97 11 87 iia 98 111 98 iv 98 v 104 vi 106 vii 98 vila 98 viii 98 ix n1 x 110 xi 87 xii 98

. 15.1 ORIGINAL 1-1 97 1-2 97 1-2a 97 1-2b 92 1-2c 97 1-3 87 1-4 53 1-5 87 1-6 98 1-7 98 1-8 98 1-9 98 1-10 98 2-1 69 2-2 87 2-3 69 2-3a 87 2-3b 87 2-3c 87 2-4 87 2-5 87 2-6 87 2-7 83 2-8 CHANGE NO 49 2-9 83 2-10 83 2-11 87 3-0 97 3-Oa 97 3-1 97 3-la 97 (page 1 of 8)

L___-___-____.

. 3-2 97 3-2a 94 3-2b 94 3-3 97 3-3a 87 3-4 87 3-5' 87 3-5a 87 3-5b 87 3 - 97 3-7 97 3-8 98 3-9 98  ;

3-10 87 3-11 87 3-12 97 3-13 97 3-14 86 3-14a 86 3-15 97 3-15a 87 3-15b 87 3-16 97 3-16a 87 3-17 97 3-17a ~ 90 3-18 90 3-18a 90 3-18b 90 3-18c 90 3-19 97 3-19a 97 3-20 97 3-21 97 3-22 97 3-22a 97 3-22b 97 3-23 105 3-23a 105 3-23b 105 3-24 105 3-24a 105 3-25 93 3-25a 99 3-26 99 3-26a 99 3-26b 93 3-27 97 3-28 CHANGE N0 49 3-29 CHANGE NO 31 3-30 CHANGE NO 31 3-30a 97 3-30b 93 3-30c 93 3-31 97 1 3-32 87  !

3-32a CHANGE NO 26 (page 2 of 8)

i- *

, 3-33 CHANGE NO 48 3-33a 87 3-33b 87 3-33c 87 3-33d 87 3-33e 87 3-33f 87 3-33g 87 3-33h 87

- 3-341 - - 87 3-33j 87 3-33k 87 3-34 93 3-35 87 ,

3-36 97 l 3-37 ORIGINAL 3-38 87 3-38a 93 3-38b 93 3-3Sc 93 3-38d 93 3-38e 93 3-38f 93 3-38g 93 3-38h 93 3-381 97 3-38j 97 3-39 101 3-40 87 3-40a 87 3-41 94 3-42 94 3-42a 94 3-42b 94 3-42c 94 3-42d 94 3-42e 94 3-42f 94 3 42g 94 3-42h 94 3-421 94 3-42j 94 3-43 94 3-43a 94 3-43b 94 3-43c 94 3-43d 94 3-44 79 3-45 86 3-46 87 3-46a 97 3-46b 97 3-47 97 3-48 ORIGINAL 3-49 ORIGINAL 3-50 ORIGINAL 3-51 110 3-51a 110 3-51b DELETED 3-51c DELETED (page 3 of 8)

3-51d DELETED 3-51e DELETED 3-52 70 3 85 3-54 85 3-55 85 3-55a 85 3-55b 85 3-55c 94 3-56 85 3-MC' 85 3-56b 85 3-56c 94 3-56d 85 3-56e 107 3-57 85 3-57a 85 3-57b 94 3-58 85 3-59 85 3-60 98 3-60a 98 3-61 98 3-62 98 3-63 98 3-63a 98 3-64 98 3-65 98 3-66 98 3-67 98 3-68 98 3-69 98 3-70 98 3-71 98 3-72 98 3-72a 98 3-73 98 3-74 98 3-75 98 3-76 98 3-77 98 3-78 98 3-79 98 3-80 53 3-81 98 3-82 98 3-83 98 3-84 98 3-85 98 3-86 98 3-87 98 3-88 98 3-89 53 3-90 98 3-91 98 3-92 98 3-93 94 3-93a 94 (page 4 of B)

3-94 88 3-95 88 3-96 95 4-0 102 4-0a 97 4-1 97

,i 4-2 87 4-3 78 4-4 99 4 ' ORIGINAL 4-6 CHANGE N0 31 4-7 ORIGINAL 4-7a 41 4-7b 98 4-7c 94 4-7d 93 4-7e 93 4-7f 97 4-78 97 4-8 97 4-8a 97 4-9 98 4-9a 98 4-10 104 4-11 76 4-12 104 4-12a 76 4-12b 76 4-13 97 4-14 87 4-15 97 4-16 97 4-16a 97 4-17 102 4-18 102 4-18a 97 4-19 76 4-20 87 4-21 58 4-22 CHANGE N0 4 4-23 CHANGE N0 4 4-24 87 4-25 95 4-26 76 4-27 76 4-28 87 4-29 93 4-30 94 4-31 94 4-32 102 4-33 87 4-34 94

) 4-34a 94 4-34b 94 4-34c 94 4-34d 94 (page 5 of 8)

\; ,

la -

F . ,

c b, 4-34e l 94

'4-34f 94 4-34g 94 4-34h- 97 4-341 97 4-34j 97 4-34k 97 4-341 97 4-34m

• 97 4-T' 94 4-36 ORIGINAL 4-37 ORIGINAL 4-38 87 4-39 105 4-39a 105 4-40 87 4-41 91 4-41a 91 4-41b 97 4-41c 94 4-42 103 4-42a CHANGE NO 39 4-42b 103 4-43

. CHANGE NO 39 4-43a CHANGE NO 39 4-43b CHANGE NO 39 4-43c CHANGE NO 39 4-44 87 4-45 87 4-46 1 ORIGINAL 4-46a 87 4-46b 87 4-46c 87 4-47 110 4-47a 110 4-47b 110 4-47c 110 4-47d 110 4-47e 110 4-48 87 4-49 CHANGE NO 13 4-50 CHANGE NO 13 {

4-51 109 4-52 109 4-53 106 4-54 109 4-55 106 4-55a 109 4-55b 106 4-56 CHANGE NO 13 4-57 109 4-57a 109 4-57b 76 4-57c 76 4-57d 106 4-57e 106 4-57f 106 4-57g 106 4-57h 106 (page 6 of B)

[.- .

4-58 CHANGE NO 35 i

4-59 CHANGE N0 35 4-60 CHANGE NO 35 4-61 CHANGE NO 35 4-62 85 4-63 98 4-64 98 4-64a 98

~

4-65 98 4-C # 98

.4-67 98 4-68 98 4-69 98 4-70 98 4-71 98 4-71a 98 4-71b 98 4-72 98 4-72a 98 4-72b 98 4-72c 98 4-72d 98 4-72e 98 4-73 98 4-73a 98 4-74 -

98 4-75 98 4-76 98 4-76a 98 4-76b 98 4-77 98 4-78 98 4-79 98 4-80 98 4-81 98 4-82 98 4-83 98 4-84 98 4-85 98 4-85a 98 4-85b 98 4-86 98 4-87 87 4-88 53 4-89 98 4-90 53 4-91 94 4-92 94 4-93 88 4-94 88 4-95 95 5-1 98 5-la 98 5-lb 98 5-Ic 98 5-Id 98 (page 7 of 8)

5-2 87

, 5-3 87 5-4 87 5-5 87 5-6 87 6-1 100 6-la 100 6-lb 100 6-2 96

- 6-2a - - 100 6-2b 100 6-3 96 6-4 100 6-5 98 6-6 100 6-7 96 6-8 96 6-9 96 6-10 98 6-10a 96 6-11 100 6-12 97 6-12a 98 6-12b 98 6-12c 98 6-12d 98 6-12e 98 6-12f 98 6-12g 97 C-12h 98 6-124 96 6-13 63 6-14 110 6-15 53 6-16 53 6-17 98 6-18 98 6-19 98 6-20 96 6-21 53 6-22 80 (page 8 of 8)

' RANCHO SECO UNfT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES PJLqf Table OPERATIONAL MODES 1-2c 1 '. 2-1 1-10 1.9-1 ~~ FREQUEMC4-NOTATION l

2. 3 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 APPLICABILITY OF SPECIFICATIONS 3.0.3 AND 3.0.4 3-Oa 3.0-1 3.3-1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES 3-22b 3.5.1-1 INSTRUMENTS.0PERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY 3-38e REQUIREMENTS 3.5.7-1 EMERGENCY SHUTDOWN INSTRUMENTATION 3-38j 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3-41a 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3.7 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-43b 3.12-1 DELETED 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3-56b,c 3.14-2 INSIDE SUILDING FIRE HOSE STATIONS 3.14-3' CARBON DIOXIDE SUPPRESSION ZONES 3-56d.e 3-57a,b 3.14-4 FIRE HOSE STATIONS 3.15-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 L

3.16-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-64 3-83 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-86 3.22-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 3-95 3.29-1 METEOROLOGICAL MONITORING INSTRUMENTATION APPLICABILITY OF SPECIFICATIONS 4.0.2 AND 4.0.3 4-Oa 4.0-1 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 Amendment No. 68, 80, 85, 87, 88, 94, 97, 98, 110 lx u_______.____.._____. _ _ _ _ . _ _

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS LIST OF TABLES 1Ahlft P_A2ft 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING. FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY HITHDRAHAL SCHEDULE AT DAVIS-BESSE 1 4-12b.

4.6-1 DIESEL GENERATOR TEST SCHEDULE 4-34j 4.6-2 ADDITIONAL RELIABILITY ACTIONS 4-34k 4.14-1 DELETED l 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b c 4.17-4 SPECIAL PERIPHERAL GROUP TUBES 4-57d-g 4.17-5 SPECIAL LANE REGION GROUP TUBES 4-57h 4.19-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4

• SURVEILLANCE REQUIREMENTS 4.21-1 RADIOACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-70 4.21-2 RADI0 ACTIVE LIQUID HASTE SAMPLING AND ANALYSIS PROGRAM 4-72b 4.22-1 RADI0 ACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4-88 4.34-1 METEOROLOGICAL MONITORING INSTRUMENTATION 4-94 6.2-1 MINIMUM SHIFT CREW COMPOSITION 6-2 Amendment No. 28, E6, 76, 88, 94, 96, 97. 98, 106, 110 x

b 3 s:,  :,.

L.:

RANCHO SECO UNIT 1

. TECHNICAL SPECIFICATIONS.

. Limiting Conditions for Operation ,

i

' Restriction of use of-the Reactor Building polar crane over the steam

. generator compartments during the time when steam could be formed from dropping a load on'the steam generator or reactor coolant piping resulting L 'in rupture ofihLsystem is required to protect against a loss of coolant accident.

l I

f 3-50

{

~

RANCHO SECO UNIT 1 L

TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.12 SNUBBERS All snubbers shall be OPERABLE. The only snubbers excluded from this requirement are those installed on nonsafety-related systems and then ongif their failure or failure of the system on which tTey are Tristalled would have no adverse effect on any safety-related system.

Aeolicability When the reactor system is at HOT SHUTDOWN, HOT STANDBY, STARTUP or P0HER OPERATION. During COLD SHUTDOWN, REFUELING SHUTDOWN and REFUELING OPERATION, only snubbers located on systems required to be OPERABLE for nuclear safety.

Action With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> either:

1. replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.14c on the supported component, or

2. declare the supported system inoperable and follow the appropriate specification statement for that system, or

3. modify supports such that the supported component and the supports will be OPERABLE and within the design basis of the plant. All such changes will be subject to the provisions of 10 CFR 50.59 and will be reflected in the records required by Specification 4.14f. Also perform an engineering evaluation of the as-found condition per Specification 4.14c. '

Bases Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore required that all snubbers required to protect the primary coolant system or any other safety system or component be OPERABLE. l Amendment No. 77, 110 l 3-51

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation TABLE 3.12-1 SAFETY RELATED HYDRAULIC SNUBDES ehe .. wMd This Table has been deleted.

Amendment No. 77, 110 3-51a

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS

' Surveillance Standards 4.14 SNUBBERS l Each snubber shall be demonstrated OPERABLE by performance of the l following: '

i

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 snubber:, Tf less than l  !

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

No. Inoperable Snubbers Subsequent Visual Der Insoettion Period Inseettion Period

• O 18 months e 25%

1 12 months e 25%

2 6 months e 25%

3, 4 124 days e 25%

5,6,7 62 days e 25%

8 or more 31 days e 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.

b. Visual Insoection Accentance Criteria Visual inspections shall verify (1) that there are no visible indications 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. Snubbers 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 remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is

• The inspection interval shall not be lengthened more than one step at a time and Definition section 1.9 does not apply.

Amendmant No. 77, 110 4-47

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards functionally tested in the as found condition and determined OPERABLE per Specification 4.14d or 4.14e. However, when the l fluid reservoir of a hydraulic snubber is found to have the reservoir gort uncovered, the snubber shall be determined

~

_ inoperabTe and may be determined OPERABLE via functional testing if the test is started with the piston in tha as-found setting, extending the piston rod in the tension mode direction.

c. Functional Tests At least once per REFUELING INTERVAL, a representative sample (10% of the total of each type of snubber (mechanical or hydraulic) in use in the plant) shall be functionally tested either in place or in a bench test. For each snubber that does not meet the functional test acceptance criteria of Specification 4.14d or 4.14e, an additional 10% of that type of snubber (mechanical or hydraulic) shall be functionally tested.

The representative sample selected for_ functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. Review shall ensure l as far as practicable that the selected snubbers are representative of the various configurations, operating environments, and the range of size and capacity of snubbers of each type (mechanical or hydraulic).

In addition to the regular sample, snubbers which failed the previous functional test and were reinstalled 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. These snubbers shall not be included in the random sample and the results of these tests shall not be used to determine additional testing requirements.

If any snubber selected for functional testing either fails to lockup or fails 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 same defect shall be functionally tested. This testing requirement shall l

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

Amendment No. 77, 110 4-47a

a. s ~

(.

' RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s)

. were adm"ly affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.

4

d. Hydraulic Snubbers Functional Test Accentance 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 Snubber Functional Test Accentance 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 that 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 load, the ability of the snubber to withstand load without displacement shall be verified.

f. Snubber Service Life Monitorina A record of the service life of each snubber, the date at which the designated service commences and the installation and maintenance records on which th6 designated service life is based shall be maintained as required by Specification 6.10.2n.

Amendment No. 77, 110 4-47b

}

L

[. . _ _ _ __ ________ - _ __

.e .

t-RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards y

o Concurrent with the first inservice visual inspection and at least once per REFUELING INTERVAL thereafter, the installation and maintenance records for each snubber shall be reviewed to

- verify _tht. the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber 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 re-evaluated 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 re-evaluation, replacement or reconditioning shall be indicated in the records.

Bases 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 250 may not be used to lengthen the required inspection interval. Any inspection whose results requira 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 direct 13 related to rejection of the snubcar by visual inspection, or are similarly located or exposed to the fame environmental conditions such as temperature, radiation, and vibration.

Amendment No. 77, 110 4-47c

V .

.\*

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards When a snubber is found inoperable, an engineering evaluation is performed, in addi.tiga to tha_datarmination 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 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 10% sample of the installed snubbers wil'l be functionally tested during plant shutdowns at REFUELING INTERVALS. Observed failures of these sample snubbers shall require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers will each be. treated as a different entity for tne above surveillance programs.

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 included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical basis for future consideration of snubber service

. life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.

It is the intent of Specification 4.14 to replace / recondition and functionally test all snubbers within a ten refueling interval period. In no case will re-evaluation of any snubber's service life allow more than ten refueling intervals to pass before replacement / reconditioning and functional testing.

Amendment No. 77, 110 4-47d

RANCHO SECO UNIT.1 TECHNICAL SPECIFICATIONS' Limiting Conditions'for Operation TABLE 4.14-1

! QESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS

- FUNCT49hirLLY TESTED ONLY AS REOUIRED BY THE

. SNUBBER SEAL REPLACEMENT PROGRAM This Table has been deleted.

i Amendment No. 77, 110 4-47e

_ . . _ _ _ . _ . - _ . . _ _ . - _ _ _ _ _ . _ = . _ - . . _ _ _ _ . _ _ _ _ - _ - _ . _ - - -

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls

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

c.. Recorde ^' 'acility 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 or operational cycles for those facility components designed for a limited number of transients or cycles.

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

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

i. Records of Quality Assurance activities required by the QA Manual.

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

k. Records of meetings of the PRC and the MSRC.

1. Records for Environmental Qualification which are covered under the provisions of paragraph'6.14.

m. Records for the Radiological Environmental Monitoring Program. *

n. Records of the service lives of all hydraulic and mechanical snubbers including the date at which the service life commences and associated installation and maintenance records.

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 - Deleted Amendment No. 28, 0/ddt/difdd/10/24/80, 53, 77, 98, 110 6-14

j ,

RANCHO SECO TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES AS OF 06/29/89 APPENDIX B 4

PAGE NUMBER AMENDMENT NUMBER

- 1--- 98 11 ORIGINAL 1 45 2 ORIGINAL 3 ORIGINAL 4 53 5 DELETED 6 DELETED 7

DELETED 8 DELLTED 9 DELETED 53 10 DELETED 53 11 DELETED 53 12 DELETED 53 13 DELLTED 53

. 14 DELETED 53 15 DELETED 53 16 DELETED 53 17 DELETED 53 18 DELETED 53 19 DELLTED 53 20 DELETED 98 21 DELETED 98 22 DELETED 53 23 DELETED 53 24 DELETED 53' 25 ORIGINAL 26 45 27 ORIGINAL 28 ORIGINAL 29 45 30 DELETED 31 DELLTED 53 32 DELETED 53 33 DELETED 53 34 DELETED 53 35 DELETED 53 36 DELETED 53 37 DELETED 53 38 DELETED 53 39 DELETED 53 1 40 DELETED 53 41 DELETED 53 42 CHANGE NO 24 43 CH/.NGE NO 24 (page 1 of 2)

i .

- ,i 44 CHANGE NO 24 44a 53 45 53 1

46 ORIGINAL 47 45 48 CHANGE NO 24 49 CHANGE NO 24 50 DELETED 45 (page 2 of 2)

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