ML20214K380

Proposed Tech Spec 3/4.4.11, Reactor Vessel Head Vent Sys. Justification & NSHC Encl

ML20214K380
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/20/1987
From:	DUKE POWER CO.
To:
Shared Package
ML20214K355	List: ML20214K354 ML20214K380
References
GL-83-37, TAC-55821, TAC-55822, NUDOCS 8705280424
Download: ML20214K380 (21)

Text

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. i ATTACHMENT IB J

PROPOSED TECHNICAL SPECIFICATION REVISION.

I DATED SEPTEMBER 6, 1984 3/4.4.11 REACTOR COOLANT SYSTEM VENTS t

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4l REACTOR COOLANT SYSTEM  !

l 3/4.4.11 REACTOR COOLANT SYSTEM VENTS g

LIMITING CONDITION FOR OPERATION i 3.4.11 At least one reactor coolant system vent path consisting of at least two valves in series powered from emergency buses shall be OPERABLE and closed

• at each of the following locations:

a. Reactor Vessel head

b. Pressurizer steam space APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With one of the above reactor coolant system. vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent' path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within 6 l

hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• For the plants using power operated relief valve (PORV) as a vent path, PORV block is not required to be closed if the PORV is operable.

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l MCGUIRE - UNITS 1 AND 2 3/4 4-40 l '

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b. With both of the above reactor coolant system vent paths inoperable; maintain the inoperable vent path closed with power removed from the valve actuators of all the valves in the inoperable vent paths, and restore at least one of the vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1. Verifying all manual isolation valves in each vent path are locked in the open position.

2. Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.

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l MCGUIRE - UNITS 1 AND 2 3/4 4-41 I

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S ATTACIDENT 2 TECHNICAL JUSTIFICATION AND SIGNIFICANT HAZARDS CONSIDERATIONS 1

. Attachment 2 Page 1 TECHNICAL JUSTIFICATION AND SIGNIFICANT HAZARDS CONSIDERATION INTRODUCTION By letter dated September 6,1984 Duke proposed a technical specification change in response to NRC Generic Letter 83-37 and NRC letter dated August 3, 1984. The proposed specification was based on the model provided by GL 83-37 with the exception that the requirement to verify the flowpath was not included. Subsequently, discussions have taken place between Duke and the NRC and this supplement to the previous submittal has been prepared. This supple-ment:

a. Re-assesses the existing McGuire specifications to the model pro-vided by GL 83-37,

b. Proposes an LCO and surveillance for the Reactor Vessel Head Vent System which includes verification of flow through the vent path, and

c. Expands the Bases that had been provided in GL 83-37.

TECHNICAL DISCUSSION The design of the McGuire Reactor Coolant System (RCS) Vent System was pro-vided in response to TMI Item II.B.1 by Duke letters dated May 23, 1980, September 8,1980, February 6,1981, and August 26, 1981. The NRC review and acceptance of this design is contained in McGuire SER Supplements 4 (dated January 1981) and 6 (dated February 1983). Subsequently, the design of this system has been reflected in the updated McGuire Final Safety Analysis Report in Chapters 1.8 and 5.5.15.

The RCS Vent System is comprised of two subsystems - the Reactor Vessel Head Vent System and the Power Operated Relief Valves (PORV) located on the pres-surizer. GL 83-37 provided model technical specifications for the entire RCS Vent System. (For convenience these are provided at the end of this attach-ment.) In light of recent activities within the industry and NRC to improve technical specifications, Duke has reassessed the model provided by GL 83-37.

Of particular concern was the creation of multiple LCOs and ACTIONS for the PORV by adoption of the GL 83-37 model in its entirety.

As noted in Attachment 1, there presently exists in the McGuire Technical Specifications, two specifications that control the PORV's - 3/4.4.4 and 3/4.4.9.3. The adoption of the GL 83-37 model would add a third. With respect to the GL 83-37 model, the LCO requires that one PORY (closed) and its vent path be operable. In this instance, a footnote indicates that the block j valve is not required to be closed if the PORV is operable. This specifica-tion is applicable for Modes 1, 2, 3, and 4. Existing specification 3/4.4.4 '

Relief Valves also contains requirements for the PORV and its block valve to be operable for Modes 1, 2, and 3. (It is noted here that Specification I 3/4.4.9.3 requires a vent path when in Mode 4 when the temperature of any RCS cold leg is less than or equal to 300'F. Practically speaking this will be met by two PORV's with lif t settings less than or equal to 400 psig.)

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, Attachment 2 Page 2 The PORV flowpath consists of 3" diameter piping and larger, as noted in the attached portions of FSAR Figure 5.1-2. Duke considers that there is no need to verify this piping is capable of flow due to its large diameter. Further, such a flowpath verification test would require passing flow through the PORV's and could damage the valves. In fact the stroking of the PORV's as required by Specification 3/4.4.4 and the McGuire IST Program requires that the block valve be closed to prevent such damage.

With Mode 4 defined (Definition 1.13, Table 1-2) as average RCS temperature less than 350*F, there is 50*F between the applicability requirement of existing technical specification and the applicability within the GL 83-37 model. Practically speaking, this temperature difference is of little con-sequence. For example, during unit shutdown, the PORV is required to be operable through Mode 3. (3/4.4.4) PORV testing is not normally conducted during the transient condition of plant shutdown. The PORV is required to be operable prior to entry into Mode 4 with temperature less than 300*F (4.4.9.3.1.a). Regardless of the results of such surveillance the plant will still be shutdown. Specification 3/4.4.9.3 applies when in Mode 5 (less than 200'F). Thus, the conclusion that PORV operability will be maintained throughout Modes 1 through 4, or the plant will be shutdown.

In conclusion, Duke considers that the existing specifications which control operability of the PORV's and their flowpaths provides assurance that they will be able to function as an RCS vent path to fulfill the function provided for in TMI Item II.B.1. No additional specifications are required for this portion of the RCS Vent System.

The remaining portion of the RCS Vent System is the Reactor Vessel Head Vent System. FSAR Figures 5.1-1 and 5.1-2 (attached) show the piping configuration of this system. Duke has reviewed the model provided by GL 83-37 and has made several revisions as indicated in Attachment 3. For Staff convenience, a smooth-typed version is also provided. The revisions are as follows:

a. The heading is revised to reflect that this LCO applies specifically to the Reactor Vessel Head Vent System. The style of presentation is consistent with existing McGuire specifications.

b. LCO 3.4.11 has been rewritten to specifically apply to the Reactor Vessel Head Vent System. (As noted previously, existing specifica-tions cover operability of the PORVs and their flowpaths which ,

provides assurance that the vent path from the pressurizer steam '

space is operable. The requirement for vent paths from the " Reactor coolant system high point: is neither part of the licensing bases for McGuire nor required for Westinghouse NSSS.) The footnote is deleted as it is no longer needed.

c. In Action "a", reference is made to the reactor vessel head vent path rather than reactor coolant system vent path, consistent with the objective of the specification,

d. In Action "b",

paths consistentreference is made to both reactor vessel head vent with above.

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Attachment 2

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e. Surveillance 4.4.11 has been rewritten to refer to reactor vessel-head vent path consistent with above. Also, surveillance 4.4.11.1 is deleted as there are no manual isolation valves in the vent paths and surveillance as such is unnecessary. (See FSAR Figure 5.1-2) l' The remaining surveillances have been renumbered and the system designation in new surveillance 4.4.11.2 is revised consistent with i above.

4 Duke intends to use temperature rise as the means to' verify reactor vessel head vent flowpath. Other means that could be used, if necessary, include l acoustic monitoring.

1 Finally, Duke has revised the Bases of Technical Specifications to more clearly reflect the proposed specification 3/4.4.11. Also note that Duke has included revised index pages IX and IVII which had not been previously in-j- cluded. These latter two items were not previously provided to NRC.

i l SIGNIFICANT HAZARDS CONSIDERATION This submittal supplements that which had been previously provided by my

• letter dated September 6, 1984. The significant hazards consideration pro-vided then remains technically valid. The Federal Register Notice was pub-lished September 11, 1985. This notice indicated that the amendments would j

add operability and surveillance requirements for the Reactor Coolant System

] (RCS) Vent System. The changes from the previous proposal have been discussed

) earlier in this attachment. Duke has concluded that his'new proposed amend-ment does not involve a significant hazards consideration. The basis for 'the l no significant hazards consideration determination follows.

l The RCS Vent System is an installed system required by TMI Action Plan Item II.B.1 to provide for post-accident venting of noncondensible gases from the high points of the reactor coolant system.' The McGuire design provides vent paths from the pressurizer steam space and the reactor vessel head. Existing McGuire specifications provide assurance that the vent path from the pressur-izer steam space is operable. The proposed amendments would add Technical' Specification 3/4.4.11 and an associated bases to provide operability and I- surveillance requirements for the Reactor Vessel Head Vent System.

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The proposed change does not involve a significant hazards consideration because operation of McGuire in accordance with this change would not:

j 1) Involve a significant increase in the probability or consequences of  ;

an accident previously evaluated. The change adds limitations, '

restrictions, and surveillances not presently included in technical l specifications. There is no change required to the actual system as installed. Therefore, this change cannot increase the probability or consequences of an accident previously evaluated.

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. Attachment 2 Page 4

2) Create the possibility of a new or different kind of accident from any previously analyzed. The change adds limitations, restrictions, and surveillances not presently included in technical specifications. There is no change to the hardware of the actual system, as installed. No modifications are necessary to implement the specified surveillances. The addition of requirements does not and cannot create the possibility of a new or different kind of accident.

3) Involve a significant reduction in a margin of safety. The change adds limitations, restrictions, and surveillances not presently included in technical specifications. There is no impact on the margin of safety present in the as-installed RCS vent system. The addition of these additional requirements will not reduce the margin of safety.

The Commission has provided guidance concerning the application of its stan-dards set forth in 10CFR 50.92 for no significant hazards considerations by providing certain examples published in the Federal Register on April 6,1983 (48FR 14870). One of the examples of an amendment likely to involve no significant hazards consideration relates to changes (ii) that constitute additional limitations, restrictions, or controls not presently included in the Technical Specifications. The proposed amendments of the Technical Specifications match the example because they would impose additional limi-tations for operation and additional surveillance requirements for a newly installed system not presently addressed in the Technical Specifications. The proposed addition does not replace or relax any existing requirements in the Technical Specification.

Therefore, Duke has determined that the proposed amendments do not involve a significant hazards consideration.

. IJH Gzg>-37 REACTOR CCOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 At least one reactor coolant system vent path consisting of at least two valves in series powered from emergency buses shall be OPERABLE and closed

• at each of the following locations:

a. (Reactor Vessel head)

b. (Pressurizer steam space)

c. (Reactor coolant system high point)

APP.LlCABJLITY- MODF9 1. 7- 1 and a ACTION: ,

a. With one of the above reactor coolant system vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• For the plants using power operated relief valve (PORV) as a vent path, i PORV block valve is not required to be closed if the PORV is operable.

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b. With two or more of the above reactor coolant system vent paths inoperable; maintain the inoperable vent path closed with power removed from the valve actuators of all the valves in the inoperable vent paths, and b restore at least (two) of the vent paths to OPERABLE

, status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l

and in COLD SHUTD0Wil within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLAf1CE REQUIREMENTS 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

1. Verifying all manual isolation valves in each vent path are locked in the open position.

2. Cycling each valve in the vent path through at least one complete cycle of full travel from the control j room during COLD SHUTDOWft or REFUELIf1G. '

3. Verifying flow through the reactor coolant vent system vent paths during venting during COLD SHUT 00Wft or REFUELIflG.

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4 e-ATTACMENT 3 PROPOSED TECHNICAL SPECIFICATION REVISION 3/4.4.11 REACTOR VESSEL HEAD VENT SYSTEM t __

i 1

INDEX

(

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE-3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.................................... 3/4 4-30 FIGURE 3.4-2a UNIT 1 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS - APPLICABLE UP TO 10 EFPY......................... 3/4 4-31 FIGURE 3.4-2b UNIT 2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS-APPLICABLE UP TO 10 EFPY......................... 3/4 4-32 FIGURE 3.4-3a UNIT 1 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS - APPLICABLE UP TO 10 EPFY............................ 3/4 4-33 FIGURE 3.4-3b UNIT 2 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS-APPLICABLE UP TO 10 EPFY............................ 3/4 4-34

'I TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM -

WI-THD RAWA L--SCH EDU L E . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4

. . . 4. 35 Pressurizer...............................:............... 3/4 4-36 Overpressure Protection Systems........................... 3/4 4-37 3/4.4.10 STRUCTURAL

.3/4. u. o recaron verserINTEGRITY......................................

Mc40 vesr s ysn o., 3/4 4-39 3/4.5 EMERGENCY CORE COOLING SYSTEMS yjy g 3/4.5.1 ACCUMULATORS Cold Leg Injection........................................

3/4 5-1 Upper Head Injection............. ........................ 3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T > 350 F............................. 3/4 5-5 avg 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350 F............................. 3/4 5-9 3/4.5.4 [ Deleted]................................................... 3/4.5-11 6 3/4.5.5 REFUELING WATER STORAGE TANK............................... 3/4 5-12 McGUIRE - UNITS 1 and 2 IX Amendment No. (Unit 1)

Amendment No. 3 (Unit 2)

l INDEX BASES SECTION PAGE 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.................... ....... B 3/4 4-4 3/4.4.7 CHEMISTRY..................................... ........... B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY......................................... B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS..... ............. ........... B 3/4 4-7 TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS (UNIT 1).................. B 3/4 4-9 REACTOR VESSEL TOUGHNESS (UNIT 2).................. B 3/4 4-11 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E > 1 MeV) AS A FUNCTION OF EFFECTIVE FULL POWER YEARS................... B 3/4 4-12 FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER CONTENT ON SHIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550 F TEMPENkIURE.................................... B 3/4 4-13 3/4.4.10 STRUCTURAL INTEGRITY.. ..... ............................ B 3/4 4-17 3lcf. y ll Wericpt VESStk llc6 Vwr SY S TE ~

T3 3/4 9~!) ~

3/4.-5 ["ERGENeY-CORE-000t-fNG SYSTEMS 3/4.5.1 ACCUMULATORS............. .................... ........... B 3/4 5-1 3/4 5.2 and 3/4.5.3 ECCS SUBSYSTEMS. ............................. B 3/4 5-1 3/4.5.4 d

[ Deleted]. .............................. ................ B 3/4 5-2 c a

3/4.5.5 REFUELING WATER STORAGE TANK. ...... .................... B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS...................... B 3/4 6-4 3/4.6.3 CONTAINMENT ISOLATION VALVES... .......................... B 3/4 6-4 3/4.6.4 COM8USTIBLE GAS CONTROL. ...................... ......... B 3/4 6-4 3/4.6.5 ICE CONDENSER.................................. .......... B 3/4 6-5 3/4.7 PLANT SYSTEMS I 3/4.7.1 TURBINE CYCLE.... ......... ............................. B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........... B 3/4 7-3 McGUIRE - UNITS 1 and 2 XVII Amendment No.3/ (Unit 1)

AmendmentNo.)i((Unit 2)

r icost 64 QS- 3 7 VLSSEL // fef D REACTOR COOLANT SYSTEM 3fV.'/.11 REACTOR COOL /t'7 SYSTOf VENTjl 5 VS TE M

\,LI

1. ITIN.G CONDITION

- - - - --- FOR OPER_AT_ ION~

Tco o vwd L.A E" 3.4.11 ^t least onc reactor coolant system vent path consisting of at !c2 t two valves in series powered from emergency busesshallbeOPERABLEandclosedfatcachofthe fellc.:%g locat+ ens 4

4. (Rcacter Ves:ci heed) '

-b . ( Pressueifee-steam-space)--

c v--( Rea c to r-cool a n t-sys tem-h igh-point 4  !

APP _LLCABlLITY-MODF9 1 - { 1 net a ACTION: ' -

ve t.s el 4.a.d

a. With one of the above reactor ccc! ant tyrte~ vent paths inoperable, STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• for,thDplants sing powe operateli ' lief valve ORV) a a ent patp q (ORV blo'cj,Valv JsAiot re u'.r(d to b gse'd if RV is pe ra ble.

e e l

h'

1 l

I t

i %g vessel LJ

'"^re of the above reactor coc! ant sy;tco

b. With tw^ ar ,

i vent paths inoperable; maintain the inoperable vent path closed with power removed from the valve actuators of all the valves in the inoperable vent paths, and  %

restore at least {two) of the vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS v t s sel Le a-<k_

4.4.11 Each reactor ccclant system vent path shall be demonstrated OPERABLE at least once per 18 months by:

-1. "ur ;iy ing all ..anual isoleticr valves 4" eac"

- > vent--pate-arWhed 4" the Open=p0sitiGir.

,;;sf0 jl j2'.

Cycling each valve in the vent path through at least

' r.t*3 '

one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.^

se ssrI Lur ull 2,/. Verifying flow through the reactor e0c! ant vent syttem vent paths during venting during COLD SHUTDOWN or REFUELING.

6 r

REACTOR COOLANT SYSTEM 3/4.1.11 REACTOR VESSEL HEAD VENT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.11 Two reactor vessel head vent paths, each consisting of two valves in series powered from emergency buses shall be OPERABLE and closed.

APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:

a. With one of the above reactor vessel head vent paths inoperable.

STARTUP and/or POWER OPERATION may continue provided the inoperable vent path is maintained closed with power removed from the valve actuator of all the valves in the inoperable vent path; restore the inoperable vent path to OPERABLE status within 30 days or be in HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b. With both of the above reactor vessel head vent paths inoperable; maintain the inoperable vent path closed with power removed from the valve actuators of all the valves in the inoperable vent paths, and restore at least two of the vent paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor vessel head vent path shall be demonstrated OPERABLE at least once per 18 months by:

1. Cycling each valve in the vent path through at least one complete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING.

2. Verifying flow through the reactor vessel head vent paths during venting during COLD SHUTDOWN or REFUELING.

3/4 4-40 l

6 ATTACHMENT 4 REVISED BASES FOR 3/4.4.11 REACTOR VESSEL HEAD VENT SYSTEM

_v.._ - _. _ ,-

. REACTOR COOLANT SYSTEM BASES PRESSURE / TEMPERATURE LIMITS (Continued) the RCS cold legs are less than or equal to 300*F. Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either: (1) the start of an idle RCP with the sec-ondary water temperature of the stecm generator less than or equal to 50*F above the RCS cold leg temperatures, or (2) the start of a HPSI pump and its injection into a water-solid RCS.

3/4.4.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR Part 50.55a(g) except where specific written relief has been granted by the Commission pursuant to 10CFR Part 50.55a(g)(6)(1) .

Components of the Reactor Coolant System were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1971 Edition and Addenda through Winter 1972.

3.4.11 REACTOR VESSEL HEAD VENT SYSTEM Reactor Vessel Head Vents are provided to exhaust noncondensible gases and/or steam from the primary system that could inhibit natural circulation core cooling. The OPERABILITY of at least one reactor coolant system vent path from the reactor vessel head and the pressurizer steam space ensures the capability exists to perform this function. (Operability of the pressurizer steam space vent path is provided by Specifications 3/4.4.4 and 3/4.4.9.3.)

The valve redundancy of the reactor coolant system vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply or control system does not prevent isolation of the vent path.

The surveillance to verify Reactor Vessel Head Vent flowpath is qualitative as no specific size or flow rate is required to exhaust noncondensible gases.

The function, capabilities, and testing requirements of the reactor coolant system vent systems are consistent with the requirements of Item II.B.1 of NUREG-0737, " Clarification of TMI Action Plan Requirements", November 1980.

McGUIRE - UNITS 1 and 2 B 3/4 4-17